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Moreover, the energy from a nuclear reactor is a potential resource for the generation of electricity in the future. The national conference on nuclear science and technology has been organized to promote the multi-disciplinary approaches to the development and application of nuclear science and technology in Thailand. " Nuclear Technology : A Stimulus for Thai Economy " is the central theme for the seventh conference in order to focus on how nuclear research can assist in the development of the economy. It will also include the benefit and the usefulness of nuclear energy to the country. The conference will provide a forum for the presentation, discussion of up-to-date information and the latest developments in nuclear science and technology which contribute to the economy of Thailand. Program The 7th Nuclear Science and Technology Conference December 1-2,1998 Kasetsart Golden Jubilee Administration and Information Center, Kasetsart University, Bangkok Tuesday, December 1,1998 08:00 - 09:00 Registration Sutham Areekul Room : 09:00 - 09:30 Opening Ceremony - Address by the OAEP-Secretary General, Mr. Kriengsak Bhadrakom - Inauguration address by the Deputy Minister of Science Technology and Environment, HE. Mr. Porntep Techapaibul - Presentation of National Award to " Distinguish Nuclear Scientist " and " Eminent Nuclear Scientists " - Presentation of the Best Nuclear Research Award - Presentation of Token to " NST7-Supporters " 09:30 -10:00 Opening the " Nuclear Techno-Mart " Exhibition and Poster Presentation / Coffee Break 10:00 - 12:00 Panel Discussion on " Nuclear Technology : A Stimulus for Thai Economy " Panelists : Mr. Piromsakdi Laparojkit Mr. Wisit Charudul Prof. Puangtong Kraiphibul, M.D. Prof. Dr. Siranut Lamseejan Moderator : Assoc.Prof. Dr. Chaiwat Kupratakul 12:00 - 13:30 Exhibition Visit / Poster Session & Luncheon Sutham Areekul Room : Special Presentation 1 Chairperson : Assoc.Prof. Dr. Boonsong Siwamogsatham Co-Chairperson : Mr. Chuchat Thongyoi 13:30 - 14:20 The 10 MW Multipurpose TRIGA Reactor at Ongkharak Nuclear Research Center, THAILAND Invited Speakers : Mr. Brian Thurgood and Mr. Steve Worcester Kumpol Adulvit Room : Special Presentation 2 Chairperson : Assoc.Prof. Dr. Tatchai Sumitra Co-Chairperson : Mr. Poonsuk Pongpat 13:30 -14:20 Exploration of Petroleum by Nuclear Technology Invited Speaker : Mr. Nigorn Mungkung Sutham Areekul Room : Special Presentation 3 Chairperson : Assoc.Prof. Chyakrit Siri-Upathum Co-Chairperson : Mr. Manit Sonsuk 14:20 - 15:10 Industrial Products by Radiation Processing Invited Speaker : Dr. Takashi Sasaki Kumpol Adulvit Room : Special Presentation 4 Chairperson : Dr. Manoon Aramrattana Co-Chairperson : Mr. Siripone Chueinta 14:20- 15:10 Radioisotope Techniques for Problem Solving in the Oil and Gas Industry Invited Speaker : Dr. J.S. Charlton Meeting Room No.9 : Physical Science Session Chairperson : Assoc.Prof. Dr. Kate Krudpan Co-Chairperson : Dr. Pipat Pichestapong 15:10 -15:35 El : Effect of Nitrogen Ion Implantation on Hardness and Tribology of SKD11 Tool Steel Surface Mr. Saweat Intarasiri 15:35 -16:00 E2 : Neutron Radiography by 4 Types of Neutron Converter Screen Mr. Wichian Ratanatongchai Kumpol Adulvit Room : Nuclear Engineering and Technology Session Chairperson : Asst.Prof. Nares Chankow Co-Chairperson : Asst.Prof. Dr. Supitcha Chanyotha 15:10-15:35 Bl : Polymerization of Polyacrylonitrile within Zeolite Micropores Assoc.Prof. Dr. Tawan Sooknoi 15:35 - 16:00 B2 : Interactive Real-Time Simulation of a Nuclear Reactor Emergency Core Cooling System on a Desktop Computer Mr. Chaiwat Muncharoen Sutham Areekul Room : Annual Meeting of Nuclear Society of Thailand 16:00 -18:00 Panel Discussion on " Nuclear Technology and Thai Society Beyond 2000 " 18:00 - 18:30 Annual Meeting of Nuclear Society of Thailand Wednesday, December 2, 1998 08:00 - 09:00 Exhibition Visit / Poster Session Sutham Areekul Room : Special Presentation 5 Chairperson : Assoc.Prof. Dr. Thiraphat Vilaithong Co-Chairperson : Mr. Wanchai Dharmvanij 09:00 - 09:50 Synchrotron Radiation Application on Protein X-ray Crystallography Invited Speakers : Dr. Palangpon Kongsaeree and Dr. Weerapong Pairsuwan Kumpol Adulvit Room : Special Presentation 6 Chairperson : Dr. Somporn Chongkum Co-Chairperson : Mrs. Jindarom Chvacharernpun 09:00 - 09:50 Application of Electron Beam Accelerators for Industry in Thailand Invited Speakers : Mr. Gray Buetzow and Mr. Apiluk Lohachikul 09:50 - 10.10 Coffee Break Sutham Areekul Room : Special Presentation 7 Chairperson : Mr. Sirichai Kianmeesuke Co-Chairperson : Dr. Sirinart Laoharojanaphand 10:10 - 11:00 Development of Nuclear Instruments in Thailand Invited Speakers : Assoc.Prof. Virul Mangclaviraj and Asst.Prof. Suvit Punnachaiya Kumpol Adulvit Room : Special Presentation 8 Chairperson : Dr. Neungpanich Sinchaisri Co-Chairperson : Mr. Manon Sutantawong 10:10 -11:00 Area Wide Control of Fruit Fly by the Sterile Insect Technique Invited Speaker : Mr. Surarit Sri-arunotai Sutham Areekul Room : Medical Science Session Chairperson : Col. Dr. Chainarong Cherdchu Co-Chairperson : Mrs. Kainapa Rattanarujikorn 11:00 -11:25 Dl : From Radiation to Antioxidants Dr. Jarunee Thongphasuk 11:25-11:50 D2 : Diagnosis and Follow Up of Prostate Carcinoma by an in House Prostate Specific Antigen ELISA Kit at Pramongkutklao Hospital Ltc. Dr. Sunetra Dumrongpisutikul Kumpol Adulvit Room : Biological and Agricutural Science Session Chairperson : Dr. Chettachai Banditsing Co-Chairperson : Mr. Kovit Nouchpramool 11:00-11:25 Al : Reducing Microbial Contamination in Herbal Cosmetics and Raw Materials from Natural Source by Gamma Radiation Mrs. Yupa Tiengthavaj 11:25 -11:50 A2 : Quality Evaluation of Meat Products in Relation to Packaging and Irradiation Dr. Athapol Noomhorm Meeting Room No.9 : Natural Resources and Environmental Science Session Chairperson : Mrs. Sarunya Piadang Co-Chairperson : Ms. Siriratana Biramontri 11:00 -11:25 Cl : Transfer Factors of Cs137 and Sr8S for Freshwater Fish in Tropical Environment Mrs. Fookiat Sinakhom 11:25-11:50 C2 : Radioactive Radon Gas in Ground Water in Songkhla Lake Basin Mr. Suksawat Sirijarukul 12:00 - 13:20 Exhibition Visit / Poster Session & Luncheon Sutham Areekul Room : Special Presentation 9 Chairperson : Mr. Suchat Mongkolphantha Co-Chairperson : Mr. Chouvana Rodthongkom 13:20 -14:10 Social Advantage on the Peaceful Use of Nuclear Energy Invited Speaker : Dr. Yoshio Murao 14:10 -16:10 Panel Discussion on " Roles of RCA on Thai Economic and Social Development " Panelists : Prof. Makumkrong Poshyachinda, M.D. Mr. Nantakorn Boonkerd Mr. Poonsuk Pongpat Mr. Montri Kao-U-Thai Moderator : Dr. Somporn Chongkum 16:10 - 16:40 Closing Ceremony - Presentation of Award to the Winners of : the Student's Compositions on Nuclear Aspect : the High-School Student's Inventions in Science - Report by the Chairman of the NST7 Organizing Committee, Mr. Pathom Yamkate - Closing Remarks by the OAEP-Secretary General, Mr. Kriengsak Bhadrakom 16:40 - Refreshment •V NST7 The7th Nuclear Science and Technology Conference December 1-2, 1998 Kasetsart Golden Jubilee Administration and Information Center, Kasetsart University, Bangkok Time Tuesday, DECEMBER 1 Time Wednesday, DECEMBER 2 08:00-09:00 Registration 08:00-09:00 Exhibition Visit and Poster Session 09:00-09:50 Special Presentation : Special Presentation : 09:00-09:30 OPENING CEREMONY Synchrotron Radiation Application Application of on Electron Beam Accelerators Protein X-ray Crystallography for Industry in Thailand 09:50-10:10 Coffee Break 09:30-10:00 Exhibition Visit / Poster Session / Coffee Break 10:10-11:00 Special Presentation : Special Presentation : Development of Area Wide Control of Fruit Fly Nuclear Instruments in Thailand by the Sterile Insect Technique 11:00-11:50 Oral Presentations : Oral Presentations : Oral Presentations : 10:00-12:00 Panel Discussion : Natural Resources and Biological and Medical Science Session Nuclear Technology : A Stimulus for Thai Economy Environmental Science Session Agricultural Science (2 papers) (2 papers) Session (2 papers) 12:00-13:30 ExhibitionVisit / Poster Session & Luncheon 12:00-13:20 Exhibition Visit / Poster Session & Luncheon 13:30-14:20 Special Presentation : Special Presentation : The 10 MW Multipurpose Exploration of 13:20-14:10 Special Presentation : TRIGA Reactor at Petroleum Social Advantage on the Peaceful Use of Nuclear Energy Ongkharak Nuclear by Nuclear Technology Research Center, Thailand 14:20-15:10 Special Presentation : Special Presentation : Industrial Products by Radioisotope Techniques 14:10-16:10 Panel Discussion : Radiation Processing for Problem Solving in Roles of RCA on Thai Economic and Social Development the Oil and Gas Industry 15:10-16:00 Oral Presentations : Oral Presentations : Physical Science Session Nuclear Engineering 16:10-16:40 CLOSING CEREMONY (2 papers) and Technology Session (2 papers) 16:00-18:00 Panel Discussion : Nuclear Technology and Thai Society Beyond 2000 16:40 - Refreshment 18:00-18:30 Annual Meeting of the Nuclear Society of Thailand eu 1. lf119-3lJgnW'lJ'33Jl^}l«a'U9-3iYia1'W9'WlflPl S-l The 10 MW Multipurpose TRIGA Reactor at Ongkharak Nuclear Research Center, THAILAND B. Thurgood and S. Worcester Ongkharak Nuclear Research Center - The Role of the Consultant Andreas Jacobi, Jr. and Laurent de Haller 2. nTsam'oilTfiiiaajjIfitjmfiT'VjTarj'Siifiatj? s-2 •uni wni Exploration of Petroleum by Nuclear Technology Nigorn Mungkung 3. Industrial Products by Radiation Processing S-3 Takashi Sasaki 4. Radioisotope Techniques for Problem Solving in the Oil and Gas Industry S-4 J.S. Charlton 5. Synchrotron Radiation Application on Protein X-ray Crystallography S-5 Palangpon Kongsaeree 6. fmM Electron Beam ismjqflfTl'rIfmj/1'wiina S-6 Application of Electron Beam Accelerators for Industry in Thailand Gray Buetzow and Apiluk Lohachitkul 7. niii^M'wiifi^a-a^aTViYn^wimaEi'sl'W'iJ'SsmfiiyiEJ s-7 Development of Nuclear Instruments in Thailand Virul Mangelaviraj and Suvit Punnachaiya 8. ni?ii!)^wua^ni^ujja^T^wa1^ani^lvmnwniii1'HuiJ^ifl'W'H^''u S-8 Area Wide Control of Fruit Fly by the Sterile Insect Technique Surarit Sri-arunotai 9. Social Advantage on the Peaceful Use of Nuclear Energy S-9 Yoshio Murao nmviww A-i mminum l vnim iwzivuuz nntytm im flb jm Reducing Microbial Contamination in Herbal Cosmetics and Raw Materials from Natural Source by Gamma Radiation Yupa Tiengthavaj, Suwimol Jetawattana, Kwanyune Sripaoraya, Suwanna Charunuch and Phongpraphan Susanthitapong A-2 wa'U9>3fn^fiiEJT3^pi0^€uin UV\Z M.E.A. Ingles Quality Evaluation of Meat Products in Relation to Packaging and Irradiation Athapol Noomhorm and M.E.A. Ingles A-3 Na'ua^i^mifiujJieianmiiafi'wuiJa^qQiinn'ua-amQnfr^u^ 31 Effect of Gamma Radiation on Quality Changes of Fresh Ground Beef Saovapong Charoen and Kovit Nouchpramool A-4 N mfmn 41 ^tlw «?tn iksflniumffjniYY ut\t istiiva N-Fixation of Soybean and Residual Effect from N-Fixation of Soybean to Rice Yield in Rice-Soybean Cropping System Using N-15 Technique Chitiraa Yathaputanon, Porapimol Chaiwannakupt, Jariya Prasartsrisuparb and Thienchai Arayangul • v A-5 fiTsmuiJ'ssBnBiiTHnnwapin-iPiwin'ua^ivB A. Niger Tcnrjni'S«iEJ?^0Wm<'bT8iapi 58 mim tivmm ims nnmivii inififfuminAif Increased Citric Acid Production of A. Niger by Ultraviolet Irradiation Orawan Suksudej and Chanin Phangarakrachadet A-6 fn^n«iSQlH!nUfl3J'WnftlV1En««0-3'H'Wa'wiEJNn (Plutella xylostella L.) 64 ibsrnia iifnib>a ims m^wi Studies on Biology and Ecology of the Diamondback Moth (Plutella xylostella L.) Wanitch Limohpasmanee, Pravait Kaewchoung and Ajaya Malakrong A-7 g^ 1liJI^5 80 infl tMM imJtjn mnjuu The Cultivation of Antagonistic Bacteria in Irradiated Sludge for Biological Control of Soft Rot Erwinias : Screening of Antagonistic Bacteria for Biological Control of Soft Rot Erwinias Ngaranit Sermkiattipong, Leelaowadee Sangsuk, Penkhare Rattanapiriyakul, Surang Dejsirilert and Niphone Thaveechai A-8 rtnmVWmiVWKft^milYi^VmiliitlSlKKalll Bactrocera dorsalis (Hendel) YiQ'mTalT'm'HSjm 90 Studies on Mating Competitiveness of Sterile Oriental Fruit Fly, Bactrocera dorsalis (Hendel) Wanitch Limohpasmanee and Suchada Segsarnviriya A-9 TiJ?uniJjniiil?siSyfli Population Estimation with Mark and Recapture Method Program Wanitch Limohpasmanee and Pravait Kaewchoung B-i dfl^i^QSmeiii'Tf'V'wnie^'HaaTaiavl'uiiitjl'ui'wi'U'ga/iifi'ua^^TQ'laYi 115 *CTU aiitfea OTvtaeJ Hfii Polymerization of Polyacrylonitrile within Zeolite Micropores Tawan Sooknoi, Artit Ausavasukhi, Wischalee Setasuntorn, Araya Kittivanichawat and Theerawat Mongkolaussavarat B-2 g^ VU 127 ms George Bereznai Interactive Real-Time Simulation of a Nuclear Reactor Emergency Core Cooling System on a Desktop Computer Chaiwat Muncharoen, Supitcha Chanyotha and George Bereznai B-3 nifl'ws^fnJ'su'iJi-anjJUPii^nauasfniJj^Q'y'ua^ PP/HDPE 137 Radiation Improved Mechanical and Thermal Property of PP/HDPE Malinee Chaisupakitsin, Chatwali Thammit and Chaivat Techakiatkul B-4 •Hij'auiJa-auanTJfljnA 150 nTaliapf ai'Hl'iJifiiQ-jriimpiw'jpiiQU 147 mm A 150 kV Isolation Transformer for a Neutron Generator Chanchai Dechthummarong, Pijit Pratumtip, Chome Thongleurm, Pathom Vichaimongkol, Rachain Charoennugul and Thiraphat Vilaithong B-5 ^!JiJiv9JjT^acyfyisumviiiJi3iisi-3Yii^^nIpiEjlotfifif0 An Interfacing System for Radiation Surveillance Using a Radio Communication Network Thanakorn Arunsiri, Suvit Punnachaiya and Attapom Pattarasumun B-6 nit^iuiJ'S'Haaei^mifilYieiffi'HfiJ^i'w^'i'u^aYi'S'ifi'W^mQn^ 173 iua •viiWflMfju qpnfl \\vutaiitit)z ims ml* Yie-atniu Modification of a Cathode Ray Tube for X-ray Microscopy Vimol Supsongsuk, Suvit Punnachaiya and Decho Tong-Aram v B-7 m^iJa9PiiiV9q-3«9ai^iaTaminjj}Ji 186 imziwuz i^inng tu stunt ut\t Radiation Sterilization of Natural Rubber Examination Gloves Suwimol Jetawattana, Nuchanat Na-Ranong and Varaporn Kajornchaiyakul c-i v Wdtf& 201 mnfiu i ^ l J 137 85 Transfer Factors of Cs and Sr for Freshwater Fish in Tropical Environment Fookiat Sinakhom, Pattra Supaokit, Suntaree Kaewpaluek, Nanthavan Chantaraprachoom, Monta Punnachaiya and Nikom Prasertchiewchan V V c-2 unamjaBrwpi¥-3miPi9'w1^'wiiJiPiia1'yi'UPigIjj'uiiisiafTiiJtT-3'uai 215 BIT* 5wwi^mi ut\ Radioactive Radon Gas in Ground Water in Songkhia Lake Basin Suksawat Sirijarukul, Thawat Chittrakarn and Tripob Bhongsuwan c-3 wai)9-a^'wn'3Piua£^a 134 60 Effects of Acid Rain and Fertiliser on Root Uptake Cs and Co by Paragrass P. Chairattanamanokorn, N.W. Harvey and O. Kerdchoechuen C-4 WtHI9^f!J'UnfPIP19nT5ina9'W^'TU9-1 Cs-134 UBS Co-601'MVUCT'W 239 \ii\nt\ iwm anflo uas Ivifv Effects of Rain Acidity upon Mobility of Cs-134 and Co -60 in Soil S. Ruangchuay, N.W. Harvey and P. Sriyotha c-5 nnmaa'ummmsfmn'ssflitj'ija^ c-EndosuifanTuem 251 14 Mobility and Distribution of C-Endosulfan in Soils Patana Anurakpongsatora, Pannee Pakkong and Preeda Parkpian c-6 mi^n«imiifia9'wmtJ'U0-3fninfT h ^^nflinIi^iwiJi^ninnja^magri'jjjj''UPiT3S 260 Leaching Studies of Radioactive Cobalt, Cesium and Strontium of Cemented Sludge from Liquid Waste Treatment Plant Monta Punnachaiya, Fookiat Sinakhom and Pathom Yamkate c-7 cTYiia'uiSEjJJ-90 uas ^I^EJJJ-137 l filiiftl TT3JPI3 14!5ff? 'O'U'Vlilini Uf\t filial 1T51fl!TiT? In Situ Gamma-Ray Measurement Using a High Purity -Germanium Detector Tatchai Sumitra, Nares Chankow and Paratee Sarapassorn c-9 ^lui^aeiTvimualmanTmia'n 298 The Analysis of Tritium in Natural Water by Electrolysis Enrichment using Solid Polymer Electrolyte Pisit Suntarapai, Keisuke Isogai and Kaneaki Sato c-io nnuanmm'mvaufiiJ'uiila'uTu'UTmTaa 312 mm fjimnu The Removal of Technetium from Radioactive Liquid Waste Pattra Supaokit, Nanthavan Chantaraprachoom and Fookiat Sinakhom on TS Electropolishing 321 'U'Vnibsi'tfiJ Ut\Z Kazuyuki Mishima Radioactive Decontamination of Be-Reflector Handling Tools by Electropolishing Method Nanthavan Chantaraprachoom and Kazuyuki Mishima c-12 nnvTss^fiiiJJiiJ^siilo^ni^TaalpiaiBniiaon^ 329 mwrntll flUYnibs^U UflS Kazuyuki Mishima Radioactive Decontamination by Strippable Paint Nanthavan Chantaraprachoom and Kazuyuki Mishima C-13 ^ ^^i 340 Radiation Safety Assessment of 1-131 for Medical Personnel at Department of Nuclear Medicine, Siriraj Hospital Pentip Khunarak, Kun Suttsiri, Warunee Tueypo, Nut Asawachatrode and Prajuk Tanapiboonpon c-14 ni^iHTiJ1jji€UD0-3W'3ifiapinija5' Determination of Quantities of Radionuclides in Uranium Series in Soil via Gamma-ray Spectroscopy Somporn Chalermsuk and Rattana Bunsan D-i flinf^ffii0'w^00ni5u^'U¥i 363 From Radiation to Antioxidants Jarunee Thongphasuk D-2 niiiwDflEJua^pnjJwanTsin^iTffis^ TfiEii^ei'wiaiPi^iflPSA'MNapil'uT^viaiuifinisjiJ-jqgm^'i 378 vi.n. "Hty-3 tjrumn «m-avlffiiiff]fi ims w.e. mia ife^anfW Diagnosis and Follow Up of Prostate Carcinoma by an in House Prostate Specific Antigen ELISA Kit at Pramongkutklao Hospital Ltc. Sunetra Dumrongpisutikul and Col. Satit Raungdilokrut jrmtun v\® iJaMfhifn im ijtyiin^f flimm Hwusim i tin? D-4 New SNS/S and SNN/S Mixed Ligand Oxorhenium and Oxotechnetium Complexes Carrying a Pendant Nitro Group on the Monothiolate Moiety as Hypoxia Tissue Imaging 399 JaipetchT., Pirmettis I., Papadopoulos M, NockB., Maina T., Raptopoulou CP., Terzis A. and Chiotellis E. 99m Synthesis, Preparation and Quality Control of Tc-ECD Soontree Laohawilai, Jatupol Sangsuriyan, Nipawan Poramatikul, Chuchat Thongyoi, Taweesak Thantawiwatananon and Tippanan Ngamprayad D-6 fll'5^n Radiation Synovectomy 417 its; 1(8114 e^fiiTy'M a^nifwu ftut\m 9?-a«?i? lias ttmw VJUWU Optimization of Samarium-153 labeled Hydroxyapatite Particles as Therapeutic Agent for Radiation Synovectomy Ninnart Virawat, Angkanan Aungurarat, Sumrit Chingjit and Sudkanung Phumkem E-i ^i^KDii 431 Effect of Nitrogen Ion Implantation on Hardness and Tribology of SKD11 Tool Steel Surface Saweat Intarasiri, Yu Liangdeng, Thiranan Sonkaew, Somchai Sangyunyongpipat, Gobwutt Rujijanagul, Vittaya Thongchuchuay and Thiraphat Vilaithong E-2 nTsciiain'M^'itJW'3Pi"50'uTp)alitf'ainiiJat)'uw'3Pi^9^4U'UPi 446 Neutron Radiography by 4 Types of Neutron Converter Screen Wichian Ratanatongchai, Sasiphan Na Songkhla and Somporn Chongkum E-3 niftiiiJ1iJifU|jiimaij1pi£jmfiyfiT'Wa9'wiflfi4(''Hi E-4 ^ 11fi 456 The Effect of Cocktail on Radiocarbon Analysis by Direct Absorption of Carbon dioxide Nawarat Wattanapan E-5 iJfl^a^«9iiBwad9niinnViicB9ilfii'Sri}j^iiticTi'5fisaia9'UYi1u/ 468 Parameters Effect on the Solvent Extraction of Zirconium Chastbongkoch Srinyawach E-6 niiJjnts^uasnQiii^jm-w^glifHCm 484 flffyfyiToif ffoftn uflNQfuTuif u^ai flnti'viB uv\ IJTW Hard and Soft Agglomeration of Zirconia Powder Chastbongkoch Srinyawach, Archara Sangariyavanich, Nitaya Suparit and Papot Pruantonsai E-7 nT3iiunii:if9ilnm!J}J99nflinu3 E-8 hUIB Sequential ICP-AES 515 ay Accuracy Study for the Determination of Some Rare-Earth Elements in Monazite and Bastncisite by Sequential ICP-AES Nitaya Suparit, Chanchay Punelapdacha and Dusadee Ratanapra E-9 numw'uimfmfi RNAA 531 R The Development of RNAA Technique for Cadmium at PPM by Ion Exchange Alice Sirinuntavid and Chouvana Rodthongkom E-io nii#wvjiiBiififisj Development of an Analytical Technique for the Determination of Uranium-238, Uranium-235 and Uranium-234 by Alphaspectrometer Arporn Busamongkol and Ratirot Phareepart E-ll fni1lfl'51^'HllJ1}JlCw1lJ^wl'Ufril1Ha94]p1£JlB91U^^'SlP1'59'W 549 Analysis of Protein in Soybean by Neutron Activation Technique Chutima Kranrod, Nualchavee Roongtanakiat, Varavuth Kajornrith and Areeratt Kornduangkaeo E-12 msi^Baiin^^ima^iunminrinyf'UNiJ 563 Instrumental Neutron Activation Analysis for Human Hair Wichian Ratanatongchai, Wanchai Dharmvanij and Somporn Chongkum E-13 ni^iifi'5i2j'HiJ1jJifu5afia'wims;as;uS'mj^'-3a^''wnimpi'n'3Pi?a'w Am/Be 571 luvtt s55inM Tntpa Qffii'Gfinfi'tfEJ tins; turns sawn Determination of Silicon and Aluminum by Am/Be Neutron Souce Wanchai Dharmvanij, Chanchai Asvavijnijkulchai and Somporn Chongkum E-14 nmifiiiswBiqlmiJaantiaaTaaiEibifiaEjl 581 Elemental Analysis of Shells by Nuclear Technique Sasiphan Na Songkhla, Usanee Santatiwongchai, Surapong Pimjun, Chanchai Asvavijnijkulchai and Somporn Chongkum E-15 ni'3im'3is'mi''3Jjia'wn'vutj^''3aiYifi'Qf)f)ii'3i'3f-3man':B 590 Investigation of Pink Tourmalines by X-ray Fluorescent Technique Archara Sangariyavanich, Sasiphan Na Songkhla and Surapong Pimjun E-16 ni'Siiniis'Hnaf'W^iWB'j'SjJKi^TpifjiBtan'vna'Haaancri'Tt'Ucf 596 X-ray Fluorescence Analysis of Natural Corundum Chowunchun Prapunsri and Thiraphat Vilaithong E-17 mfiifi'sis'H^j'W'SiJj'WPiiJfjJifUJJinTfial'wmfi'Ufi'QiPiia'u 604 Bulk Analysis of Cement using Neutron Techniques Pantip Ampornrat, Tatchai Sumitra and Nares Chankow v v t E-18 nnni'HQCuni^'WiiJaa-aivamB-a'ua-Jinfa-j'iJgn'scuiJ'iJQ-i/i 620 T Fuel Burnup Calculation of TRR-1/M1 Reactor Mongkol Junlanan and Sunanta Patrashakorn E-19 IVi'Jio'wnjjQ'WCTfiTsIa 628 A Study of Multiple Scattering and Flux Attenuation of Fast Neutrons Inside a Cylindrical Sample by Using Monte Carlo Simulation Technique Udorarat Tippawan, Somsorn Singkarat, Suvicha Ratanarin and Thiraphat Vilaithong E-20 IlJ'SUfliJjilfl'SlSJ'HmiJnPifjJ^minUJJlGDA 642 Gamma-Ray Spectrum Analysis Software GDA Paitoon Wanabongse E-21 ms1w0§4WQifl0snfivfasrtrli4miflifi0-i 651 Application of Computer Graphics Phulsiri Ingtrakul (s) The 10 MW Multipurpose TRIGA Reactor at Ongkharak Nuclear Research Center, Thailand B. Thurgood and S. Worcester General Atomics, TRIGA Group, 10240 Flanders CT, San Diego, CA 92121, U.S.A. General Atomics (GA), has been selected to lead a team of firms from the United States, Japan, Australia and Thailand to design, build and commission the Ongkharak Nuclear Research Center near Bangkok, Thailand, for the Office of Atomic Energy for Peace. The facilities to be provided under this turnkey contract are comprised of: ® • A Reactor Island, consisting of a 10 MW TRIGA reactor that takes full advantage of the inherent safety characteristics of uranium-zirconium hydride (UZrH) fuel; • An Isotope Production Facility for the production of radioisotopes and radiopharmaceuticals using the TRIGA reactor; • A Waste Processing and Storage Facility for the processing and storage of radioactive waste from the facility as well as other locations in Thailand. The centerpiece of the Center will be the TRIGA reactor, using inherently safe technology provided by the uranium-zirconium-hydride (UZrH) reduced enrichment fuel. The reactor will be cooled and moderated by light water, and reflected by beryllium and heavy water. The UZrH fueled reactor will have a rated steady state thermal power output of 10 MW, and will be capable of performing the following : • Radioisotope production for medical, industrial and agricultural uses • Neutron transmutation doping of silicon • Beam experiments such as Neutron Scattering, Neutron Radiography (NR), and Prompt Gamma Neutron Activation Analysis (PGNAA) • Medical therapy of patients using Boron Neutron Capture Theraphy (BNCT) • Applied research and technology development in the nuclear field • Training in principles of reactor operation, reactor physics, reactor experiments, etc. The basic design of the reactor, reactor structure, auxiliary systems, reactor instrumentation and control systems and other balance of plant systems have been completed and detailed design is underway. Fuel loading and commissioning is expected by the end of 2001. ^ TRIGA is a registered trademark of General Atomics TH9900002 ^i TH9900002 Ongkharak Nuclear Research Center - The Role of the Consultant by Andreas Jacobi, Jr. and Laurent de Haller Electrowatt Engineering Ltd., Zurich, Switzerland Abstract: The Ongkharak Nuclear Research Center Project is known to have started on 26 June 1997. At that date the Contract for the turnkey delivery of the three nuclear facilities, the Reactor Island (Rl), Isotope Production Facility (IPF) and the Waste Processing and Storage Facilities (WPSF), was signed by the Office of Atomic Energy for Peace (OAEP) with General Atomics (GA). The involvement of the Consultant - Electrowatt Engineering Ltd. (EWE) - already started more than 2 years earlier than the official start of this ambitious project. Since mid 1995 EWE has been serving in a variety of functions and has been requested to perform numerous tasks in support of OAEP. By acting in the function of the Consultant, EWE was aiming firstly to help the project to proceed as quickly as possible. Secondly EWE was overseeing constantly that the quality of the Center, once finished, will meet the present state of the art, will be licensable in Thailand (or elsewhere) and will be internationally recognised as a safe, reliable and modern research and production installation. The role of EWE covers a multitude of engineering disciplines, such as architecture; civil, mechanical, nuclear, I&C and electrical engineering; nuclear and reactor physics; chemistry and radiopharmacy; economy and price estimation. Besides, EWE has to use its skills in conducting and/or supervising large projects, e.g., by appropriate scheduling, QA surveys, licensing support, document control, etc. Furthermore, EWE is actively involved in know-how transfer to Thai engineers and scientists by working in close co-operation with OAEP's project personnel and - if required - by giving special training courses. This paper presents some highlights as well as routine activities performed by EWE so far in the Project. (Exploration of Petroleum by Nuclear Technology) to.. tins Nigorn Mungkung Software Support Manager, Schlumberger Oversea S.A., Bangkok, Thailand 8-2 J( mail vi.flf.2464 ^NHwill?i5m I^uri u?(y'Mgli4ima vim mm Tertiary Tertiary «S;SnilJTUm?B?tUl'Vianiill?fffU5iyflf-3ifi^'M aUiUBSragi tYunTSaTSIIlUUUnTS'HaJSf CU (Logging) fi.flf. 1927 (vi.sf. 2470) Henri Doll I^tiimufintl Electrical Log 'U Yi.ft. 2484 ]«aSH^?I^T4fn?'V11fn7tfn51!)'Ha^B?t3 I«aH Gamma Ray Ht\% Neutron Tools l'U0-afnnSatUtnJ1ji^lK'U9n'ii Electrical Log iJitUIUJlJ VI.fr.2502 Neutron Log fjfllh JJilli'UfnflJ^smUfmW'HT'U (Porosity) uaWUlhl IT114 Gamma Ray Sand HV\Z Shale Gamma Ray pti'Unl#0Emn"^ Tfltl Gamma Ray 4/ a* *3 40 238 232 3 BI^ «it)fiy fi© K ,u ims;Th Density Logs lflt40flT5K^-3^H!n5nJJ3Jt4?lfny(f-3ft lll * V i < Moddle Energy Gamma Ray TPI«J Gamma Ray Yllla'0890n1llmm »^llJ'ds nsm Electrons ^JQ^J'tfli'HTJ m?f[njlftf)yia^-3n4U0^ Gamma Ray tfn-ainflfmib'VlsmJ V Electrons Neutron Logs lllinf fm*niJiinfUnJ0^ Hydrogen Hydrogen \\,V\Z Carbon Industrial Products by Radiation Processing Takashi Sasaki Nuclear Technology and Education Center Japan Atomic Energy Research Institute 1. Introduction Radiation processing is a method for producing chemical and physical changes in substances by exposure to ionizing radiations. The ionizing radiation could be in either form of gamma-rays, high energy electrons, or Bremsstrahlung (X-rays). Radiation sources being practically and commonly used are Co-60 or Cs-137 gamma- ray sources or electron accelerators up to 10 MV in their energy levels. X-rays are essentially the same in the nature as gamma-rays. It should be noted that the process is essentially a low temperature one in that relatively small quantities of energy are required to produce significant effects. In addition, radiation processing does not make products radioactive. In early 1950's, polyethylene was found to be crosslinked and become thermally stable or not melt-flowable by exposure to ionizing radiations. This finding was followed by radiation-induced graft polymerizations and curing of unsaturated polyester resins. These findings attracted the polymer industry very much to apply radiation chemistry for modification and processing of polymeric systems. Despite considerable amount of R & D accomplished in this field for industrial applications by mainly using Co-60 gamma rays, only a few systems have reached commercial production. The usefulness of high energy radiation for polymeric systems has been increased by the availability of electron accelerators. In 1957 Ethicon Inc., a Johnson and Johnson Company, adopted electron beam sterilization of medical sutures. The Sequoia Wire Company also adopted the irradiation of wire insulation around the same time. With the development of electron accelerators specially in lower energy levels, electron beam curing systems acquired an industrial reality in late 1960's. The total number of electron accelerators installed worldwide for polymer processing may reach one thousand at present. Major applications are crosslinking of wire and cable insulation, crosslinking of plastic films and foam, and curing of coatings. An industrial electron accelerator is known to run continuously and reliably while being able to be turned off when not in use. On the other hand, the sterilization of disposable medical devices as well as food irradiation has mostly been done using gamma radiations from Co-60. There have been about 200 gamma-irradiation facilities worldwide in 1997. This article describes the basis of radiation processing of polymers and two major applications, crosslinking and electron beam curing. 2. Basis of Radiation Processing of Polymers. 2.1 Reaction Mechanisms Ionizing radiation transfer their energy to matter through electrostatic interaction of fast- moving electrons with the electrons of the irradiated substance. Mainly ions and excited molecules are initially produced through primary and (repeating secondary ionization or excitation. These species are rapidly converted into free radicals that are, in most cases, the active chemical species to initiate further reaction: AB+ + e ionization AB A/W AB> * exitation AB+ + e • AB* neutralization AB* • A* + B • radical formation It should be noted that the formation of radicals is temperature-independent, which means that the following reactions can take place at room temperature or even at lower temperatures. Radiation-induced reactions concerned with polymeric systems can be categorized in four groups as shown in Table 1. Table 1 Radiation-Induced Polymer Reactions System Reaction 1) polymer crosslinking chain scission (degradation) 2) polymer - low mol. wt. compound e, g. chlorination 3) monomer polymerization 4) polymer - monomer graft copolymerization (reactive polymer) curing(graft + polymerization) As described in the previous chapter, crosslinking and curing have been widely industrialized using electron beam accelerators. Radiation-induced graft polymerization is very much effective for modification of polymers.especially chemically stable polymers such as polyolefines. 2.2 Factors affecting Radical Reactions 2.2.1 Effect of Oxygen Free radicals are generally much more reactive with oxygen than with monomers and form rather stable peroxide radicals or further hydroperoxides which inhibit radical polymerization. Therefore, any radical polymerization process, whether radiation-induced or catalytically initiated, should be performed under an inert condition. Crosslinking of molded plastics with electron beam can be performed in air because of less amount of air inside the materials. However, as the irradiation time increases at a lower dose rate as is the case for Co- gamma rays irradiation, oxidative decomposition may occur. 2.2.2 Dose Rate Effect The rate of polymerization, Rp, is dependent upon the concentration of free radicals, [R«], and the concentration of the reactant, [M]. Assuming a steady state of free radicals and bi- molecular termination of polymerization, the following relationship can be derived: Rp «[R.][M] ~ [I]1/2[M] where, [I] is the intensity of electron beam or the dose rate. This relationship, well known as the square root relationship, is not always valid for practical cases, which indicates the assumptions are too much simplified. It should also be noted that the rate of gel formation is not necessarily proportional to that of polymerization. Crosslinking reactions which are based on recombination of polymer radicals are independent of the dose rate in principle, but the oxidative decomposition may increase with decreasing dose rate in the case of irradiating in air, as described above. 2.2.3 Structures of Polymers While some polymer's crosslink during irradiation, others degrade as shown in Table 2. Actually, both reactions occur simultaneously and either reaction will predominant depending upon irradiation conditions. From Table 1, it can be said that a polymer of which monomer unit has tertiary carbon most likely undergoes scission by ionizing radiation. Table 2 Classification of Polymers Crosslinking Type Degradatiion Type Polyethylene -CH2-CH2- Polyisobutylene -CH2-C(CH3)2- Polypropylene -CH2-CH(CH3)- Polytetrafluoroethylene -CF2-CF2- Poly acrylamide -CH2-CH(CONH2)- Polymethacrylamide -CH2-C(CH3)(CONH2)- Polyacrylate -CH2-CH(CC-2R)- Polymethacrylate -CH2-C(CH3)(CO2R)- Poly(vinyl chloride -CH2-CHC1- Poly(vinylidene chloride) -CH2-CC12- Natural rubber -CH2C(CH3)=CHCH2- Poly-a-methylstyrene -CH2-C(CH3)(C6H5)- 3. Crosslinking 3.1 Principle of Radiation Crosslinking The interaction of radiation with a polymeric material results in producing mainly polymer radicals and hydrogen radicals. When pairs of polymer radicals combine to form 'crosslink' between two carbon-carbon atoms, the molecular weight will increase at the initial stage. As this process occurs repeatedly, the three dimensional networks will be formed. For example, the following reactions mainly occur upon irradiation on polyethylene that is one of typical crosslink type polymers (Table 2). -(-CH2-CH2-)-n AMf-** ~ CH2-CH2-CH2- + f (1) -(-CH2-CH2-)-n A/\h-+* -(-CH2-CH2-)-n* (2) ~ CH2-CH2-CH2CHCH - + e- • -(-CH2-CH(CHCH)2-)-n* (3) -(-CH2-CH2-)-n* • ~CH2 + • CH2~ (4) -(-CH2-CH2-)-n* • ~ CH2- CH ~ + H • (5) - CH 2-CH ~ + H • ~ CH=CH ~ + H2 (6) ~CH 2-CH ~ + ~ CH 2-CH • - CH 2-CH ~ - CH-CH2 ~ (7) The direct chain scission occurs as the reaction (4), but the recombination of the resultant radicals will be predominant. The reaction (7) is the formation of a new carbon-carbon bond, i. e. crosslink. Crosslinking or degradation can be promoted or retarded by irradiation conditions. As described previously, the presence of oxygen retards the formation of crosslinks. The formation of three dimensional networks in a polymeric system causes beneficial property changes such as: increased tensile strength increased form stability and resistance to deformation increased resistance to solvents improved shrink-memory property 3. 2 Industrial Applications Wire and Cable Insulation Materials Electron beam crosslinking of wire and cable insulation is widely used in industry. More than 30 % of the industrial electron accelerators in the world and more than 60 units in Japan are being used in this field (in 1996). The most common insulation materials are low density polyethylene and polyvinylchrolide. Table 3 is the comparison of electron beam and peroxide crosslinking of wire and cable insulation. go® Table 3 Comparison of EB and Peroxide Crosslinking of Wire and Cable Insulation Item Electron Beam Peroxide Energy consumption low high Line speed (m/min) fast (-500) slow (-200) Factory space less Product sizes wide-variety fixed Process control current and speed heat flow Maintenace low cost higher cost Start-up instant (no scrap) slow (many scraps) Voltage rating (kV) up to 5 50 Shelf life of insulation excellent good Capital investment high moderate Polyethylene Foams Since crosslinked polyethylene does not flow or deforms less at an elevated temperature higher than the melting point, electron beam crosslinking has been applied to produce polyethylene foam. Fig. 1 is a block diagram of the process. Polyethylene is blended with a foaming agent and then molded into a sheet or tubular form at a temperature range above melting point of polyethylene (Tm) and below the decomposition temperature of the forming agent (Tf). The molded materials are irradiated followed by heating up to a temperature above the Tf to form bubbles in the molten polyethylene. Table 3 is a list of characteristics of radiation-crosslinked polyethylene foam. The foam is widely used for packaging, interior of cars, building materials and so on. Table 3 Charasteristics of EB Crosslinked PE Foam Semi-rigid Shock Absorption Properties over Repeated Impact Low Thermal Conductivity Excellent Impact Sound Insulation Low Water Adsorption and Excellent Buoyancy Extremely Low Dielectric Constant & Loss High Dimensional Stability (Shape Retention) Orderless and Non-Toxicity Easy Processability Fine Cells and Smooth Surface (Polyethyl'ene Extrusion Blending Crosslinking (Sheet) with EB f Foaming Agent J— Foamed Foaming by Formable Sheet Y PE Sheet Heating Fig. 1 Block Diagram for Production of PE Foam Heat Shrinkable Tubes and sheets These materials are very large users of the electron beam for the essential crosslinking step that imparts the shrink-memory property. Fig. 2 shows the block diagram of the production process. After the material is irradiated to crosslink at ^( PolymerD a certain level, it is heated at a tem- Irradiation / + (Crosslinking) perature higher than the melting point of the polymer, followed by expan- Heating above m.p. sion by external force and then quick ( Expansion J cooling under the force to maintain the expanded shape. The product will Heating Quick Cooling above m.p. contract to its original form when \ !! Removal of tension heat is applied. The uses of shrink- f Products J able materials are widespread as shown in Table 5. Fig. 2 Process for Heat Shrinkable Materials Table 5 Application of Shrinkable Materials Packaging for Food and Products Insulators for Electric Parts and Joints Cnnectors for Telecommunication Cables Insulation of Oil Pipelines Corrosion Protection of Welding Line of Steel Pipe Precuring of Tire Components The use of electron beam in the tire industry has been veiled in secrecy. However, 30 units in the world (1989) and 25 units in Japan (1996) were believed to be used in this field. As shown in Fig. 3, the components are being partially pre-cured before being built into tires, and are finally cured by conventional tire-manufacturing methods. The precuring improves green strength of rubber sheets and permits use of less material with easier handling while still producing a better quality tire. Rubber(s) j • Compounding -^ ( Additives j NR S, Carbon, SBR ZiO, etc etc 1 Innerliner (Bead Wire) Bead Insulation Tread Ply Fabric J Sidewall M/r^ Assembly Molding Vulcanization Fig. 3 Tire Manufacturing Process Vulcanization of Natural Rubber Latex This field is not yet industrialized in a large scale but is expected to have potentials to grow up in near future. Semi-commercial production of rubber gloves from radiation vulcanized natural rubber latex (RVNRL) began in March in Japan by using gamma-rays at an irradiation service center. Also developed are medical devices such as optical laser balloon, drainages, and surgical gloves. The advantages of the RVNRL are as follows: absence of nitrosoamine low cytotoxicity absence of sulfur and zinc oxide transparency and softness simple process go® 4. Electron Beam Curing 4. 1 Principle of Electron Beam Curing The electron beam curing process essentially involves the application of a thin coating of a viscous prepolymer-monomer mixture (liquid) onto a substrate, followed by passage under an electron beam to solidify the coating. The original meaning of "cure" or "curing" is merely a physical change from a liquid state to a solid state. However, as described above, the reaction involved in the process is normally radical (co-)polymerization between double bond in the pre- polymer (oligomer) and monomer(s). The reaction is schematically illustrated in Fig. 4. The reaction is very fast (a matter of less than one second) due to high concentration of radicals in the mixture under a high intensity of electrons. Table 6 summarizes the advantages of the process. N Monomer(sV) ^ Coating Unsaturated Wet Film Cured Film Prepolymer Composition J (^Pigment, etc) Fig. 4 Schematic Block Diagram for Electron Beam Curing Table 6 Advantages of Electron Beam Curing Hardening at Ambient Temperature Energy Saving Applicable to Heat-Labile Substrates 100 % Solid System (Solvent-free) Less Materials and Non-Polluting Non-Catalyst Systems Long Potlife of Resins Better Weather Durability of Products Rapid Start-up and Shut-off of Power Source Rapid Curing --- High Line Speed Less Plant Space Prepolymers Radiation curable prepolymers are generally mono- or multi-functional reactive oligomers with a molecular weight of one thousand to several thousands. They provide the primary properties of the cured films such as high abrasion resistance, high tensile strength good solvent resistance and acceptable levels of hardness and flexibility. Unsaturated polyesters are well known as one group of thermosetting resins and have been used for FRP (fiber reinforced plastics) and coatings. They are normally being used as mixtures with styrene, and comparatively cheap in price. UPE-styrene mixtures can be used for wood coatings, but the cure rate is rather slow. Acrylated prepolymers (Table7) are very popular and can be cured much faster than UPE- styrene mixtures, but are generally costly. Polyene/thiol systems are very unique compared with other ones and have little effect of oxygen inhibition on the cure rate, but have troubles in odors. Table 7 Typical Acrylic Prepolymers Prepolymer Characteristics high weather durability Unsaturated acrlics Ac chemical stain resistance Ac Ac Urethane acrylate flexibility abration resistance Ac~OCNH )~AC 6 O Polyester acrylate hardness stain resistance O Polyether acrylate flexibility elongation Epoxy acrylate good adhesion chemical stain resistance Ac : Acryloyl group Monomers Prepolymers, being generally highly viscous or almost solid, are necessary to be diluted with monomer(s) to have suitable working viscosities. A monomer will influence cure rate, mechanical and physicaJ properties, adhesion residual odor, and also toxicological properties of the solutions or cured films. A variety of acrylic monomers have been developed and are available on the market. Cationic Initiation As mentioned before, polymerization can be initiated by a cationic mechanism udder a certain limited condition that is practically impossible for curing of coatings. Since the types of prepolymers that can be cured by the radical mechanism are limited, efforts have been done to develop new type of photo-initiators for enabling to cure epoxy resins by the cationic mechanism. Various kinds of aromatic onium salts of Lewis acids have been developed for this purpose. These salts are thermally stable, but photolyze to strong Lewis acids that initiate cationic polymerization. These onium salts are also usable for EB curing, although the decomposition mechanisms of them are indicated to be somewhat different with those in the UV system. Major advantages of the cationic systems are that the dose rate and the presence of oxygen do not effect the cure rate. More recently, various kinds of vinyl ethers have been developed to take advantage of their high cure rates. 4.2 Applications The electron beam curing technology covers a wide range of applications as shown in Table 8. Table 8 Application of EB Curing Coatings Wood Finishing (Forest Products) Furniture, Door, Flooring Plastics Electric parts, Plastic films (Antifog, Antistatic etc), Magnetic media Paper Gloss coating, Record albums, Folding cartons, Release paper Steel and Metal Substrates Color steel panels, Can, Automobile components Cement and Ceramic Substrates Roof tiles, Slate tiles, Ceramic tiles, Gypsum tiles, Printing Inks Intalio (security) printing, Paper package for beverages. Plastic sheets Adhesives Laminates (paper-paper, paper-plastic, paper-wood, plastic-steel) Flocking, Metalization Pressure-sensitive adhesives 84) Wood Coatings Boise-Cascade in the United States installed semi-commercial plant in 1967. Late on, companies in the western Europe introduced this technology. Although these earlier lines used scanning-type accelerator, Universal Woods Inc. later installed a linear-filament type accelerator. This company has the line where simultaneous lamination of paper and curing of top-coatings is performed by electron beam irradiation. The line, using UV and EB systems, is called a dual cure sytem, and schematically illustrated in Fig. 5. Sander Sander Paper Top EB Adhesive V Coat EB UV II Coater A _ UV Fig. 5 Dual Cure System for Wood Panel Coating. Coatings for Metal and Inorganic Substrates It has been reported that this technology can offer tremendous energy saving over thermal curing systems. However, industrial use of the technology has been rather limited by poor adhesion properties of EB-cured coatings on inorganic substrates. In the thermal curing processes the adhesion properties can be improved by thermal annealing of interface strain in the coatings. Nippon Steel Corporation, Toray Industries Inc. and others made a joint research that resulted in a successful production of electron cured high grade precoated steel sheets in 1982. Recently, this technology has been further developed for manufacturing tunnel interior panels. Another success example in production of precoated steel sheets has been made by Nissin Steel Co. The products have many varieties of three groups; EB-1 with clear image or high gross, EB- 2 with multi-color elaborated designs, and EB-3 with high functional PVC surface layer. EB curing technology has also been applied in Japan to produce cement roof tiles, gypsum tiles (for walling), and cement boards. In Germany, Otto Durr/ and Polymer Physic have developed an EB irradiation system for curing the coating of car wheel rims. These examples have shown that low energy electrons are capable of traveling in a wide range of angles and curing coatings on shaped articles. Magnetic Medias Most of major manufactures worldwide introduced laboratory EB units, and a great deal of R& D work has been performed. In 1986 TDK announced the initiation of industrial production of floppy discs, which was the first case in the world. The products have such durability as allowing 40 million passes per track to withstand and such reliability as being capable of use under extreme conditions and environment. A few EB lines are believed to be in operation for production of floppy discs. Silicone Release Coatings At present various acrylics modified silicones are available. It is claimed that the systems are commercially acceptable for application to a wide range of paper and plastic films for use in pressure sensitive adhesive labels and the sealant industry. In fact, Scholar Release Products is producing EB cured release papers. Adhesion/Lamination One of the earlier EB curing applications in this field was production of flocked plastic substrates by Bixby International Corp. (1975). Later in 1979, Metallized Products in the U.S. installed an EB line for metallizing basecoat and protective overcoat. More recently, Hallmark Cards, Inc. have developed a transfer metallization system called EB-Aluglas process, where the laminating, curing and delaminating steps are combined into one continuous operation. Pressure Sensitive Adhesives Development of radiation curable pressure sensitive adhesives (PSA) have also extensively performed, since PSA have a wide range of industrial and non-industrial uses. Most of radiation curable PSAs appeared in literatures is composed of non-reactive polymers and monomers, whilst only a few systems of typical radiation-curable formulations have been developed. It has been believed that several EB lines in the world one line in Japan has been installed for manufacturing PSA products. Printing and Graphics AGI Inc., based in Chicago, U.S.A. took advantages of EB technology in the packaging printing such as record album jackets in early 1980's. This example was followed by the Tetrapak that delivered some twenty EB units to its factories worldwide. In 1986, Mitsumura Printing Co. started to print on polyolefine sheets with EB. It is claimed by the company that EB products better stain and solvent resistances without primer coating over UV processed ones. RADIOISOTOPE TECHNIQUES FOR PROBLEM SOLVING IN THE OIL AND GAS INDUSTRY J.S. Charlton, B.Sc, Ph.D., General Manager Tracerco Australasia SUMMARY The current usage of radioisotopes in problem solving, process optimization and control in the oil gas industry is reviewed. Recent developments are described with application ranging from sub-sea, through measurements on the production platform, to studies at onshore terminals and oil refineries. 1. INTRODUCTION highly penetrating radiations may be used and for this reason the sealed source techniques described are Radioisotope technology has been used for almost based upon the use either of gamma-ray or of neutron half a century by the oil and gas industry to solve sources. problems and to help optimize process operations01. The use of radioactive isotopes to investigate the 2.1 Gamma-Ray Absorption Techniques effectiveness of well stimulation procedures and to measure the sweep-out patterns of oil and gas in A large number of useful applications is based upon secondary recovery processes is well known'23'. The the phenomenon of gamma-ray absorption. The basic applications of radioisotopes to study features of plant principles are as follows: and process operation has been less widely reported though the economic benefits deriving from such A source of gamma-radiation is positioned on one applications are very great. side of the vessel of interest and a radiation detector is positioned on the opposite side. They are then Nevertheless, there has been continuous development moved together up or down and the intensity of the in the range of application and in the design of radiation transmitted through the vessel is recorded as equipment to facilitate the use of the technology at a function of position. For a narrow beam of remote environments - such as an oil or gas platform. radiation, the intensity, I, transmitted through a Techniques for studying the operating characteristics medium of thickness x and density d is described by of processing plants and refineries have also the equation: undergone progressive improvement I = Io exp(-mdx) .(1) Applications range from down-hole studies on the well and reservoir, through sub-sea examination of where Io is the intensity of the incident radiation and production platforms and peripherals, to topside m is a constant called the mass absorption coefficient. studies on the platform and on onshore installations. If the separation of the source and detector is kept Although there are many different kinds of constant, the intensity of transmitted radiation is a application, for purposes of description they can be function of the density of the medium. Thus, as the divided into two broad categories techniques which source and detector scan through vapour a high utilize sealed sources of radiation and radioactive radiation countrate is obtained whereas, when the tracer techniques Down-hole applications, as has 'scan line' intersects a liquid or solid phase a lower been noted, are amply described in the literature and radiation countrate is observed. Changes in the for this reason they will not be considered further in intensity of the transmitted radiation therefore reveal this paper. levels and interfaces in vessels as well as internal mechanical structure 2. SEALED SOURCE TECHNIQUES The changes experienced in moving from regions of The essential feature of all sealed source techniques is low intensity to high intensity are not perfectly sharp. that the radioactive isotope remains permanently Sometimes, the reason is simply that the levels or sealed within a capsule and makes no contact with the interfaces are diffuse, but there is also an effect from plant or process material. Radiations from the source radiation scattering because wide-beam, instead of are directed at the plant vessel of interest and by narrow beam source-detector geometry is usually observing changes in the transmitted or the scattered used This is necessary because the shielding required radiation we can draw conclusions about the contents to produce narrow beam radiation would make the of the vessel Because oil production units and source container too heavy and unwieldy to use industrial plants arc of substantial construction, only In its simplest form, this technique can be used to Instruments based on the gamma-ray absorption identify and measure liquid level in a tank. phenomenon are commonly used both in offshore and Alternatively, if the source and detector are fixed in in onshore locations. Table 1 provides some one position (Figure 1) then the level in the tank will indication of usage. be recorded as it passes this point. This is the principle of the high or low level alarm ("level switch"). By using an extended detector and by angling the source beam to span the detector length, DUTY NUMBER the system can be converted into a level gauge. Level gauges generally work on the principle of On Shore Topsides Sub-Sea complete obscuration of the gamma-ray beam by the fluid in the vessel. However, if the path length through the liquid is kept short, the gamma-ray Level Alarm / transmission is a function of the liquid density Level Gauge Figure 1. Principles of Installed Nucleonic These so-called "nucleonic" gauges possess a number of Gauges For Level and Density advantages over more conventional instruments: Measurement (a) The instruments have no contact with the process material and operate either outside of the vessel or in sealed dip tubes. Thus, there are no problems in operating with corrosive, viscous or toxic liquids or with materials at high temperature and pressure C'ttttCtlT (a! Level Alarm ib) Proportional Level (b) There are no moving parts and the instruments Indicator are of rugged construction. Little or no Scurce container with maintenance is required and the reliability of retraction mfthortsm the systems is high. These are important considerations, especially so for instruments Sources r dip pipe installed sub-sea where access is difficult. ~\ Sad,at ion j dttpefors (c) The systems are intrinsically safe from an electrical point of view. Ic) Liquid Interface Position Indicator (d) Instruments can often be installed on a vessel 1 -10 e>tp ( upr I while the vessel is on line thus averting the need for a costly shut-down SHelded For these reasons, nucleonic gauges are now standard for some of the more difficult control applications Kicroconputtr Examples are given later in the paper. Voltage sicnul proportional to femperafure Relays opfrole dorms ct critical (Jens ty value 2.2 Neutron Backscattcr Technique Ano!cqu£ 'jiq-'w! prop Techniques based on the phenomenon of neutron id I Density Gouge backscatter may complement, or be used as alternatives to gamma-ray absorption methods The principle underlying these techniques is described with reference Figure 3. A Portable Gamma-Ray to Figure 2. Absorption Pipe Scanner Figure 2 Measurement of levels and interfaces using a Neutron Moderation Technique SO Vapour - 40 Fast-neutron - 30 source x_ Oil ; - 20 ^/ Watei - 10 Slow-neutron detector PortotrU ttKtcofwc \ Oit/Waier Interface D«tector output \OiLVapouf interface Lines which contain deposits and which are partially full 0 K 20 30 40 50 of oil or water can sometimes be studies using the Di&t«nc« from Baa* of Vvsael gamma-ray absorption technique and neutron backscatter technique in combination. Figure 4 shows a typical result obtained from scans carried out on a Radioisotope neutron sources emit energetic or "fast" partially full slug-catcher. The neutron backscatter neutrons Of all chemical elements, hydrogen is technique was used to determine the level of the outstanding in its ability to slow down or moderate hydrogenous liquid - in this case, condensate - and from neutrons to lower energies Thus, when fast neutrons this information, together with the results of a number of from an isotope source are directed into a hydrogenous diametric gamma-ray transmission scans made around material, the number of slow neutrons produced is, to a the pipe the radial distribution of the deposit was good approximation, proportional to the hydrogen inferred. concentration Figure 4. Measurement of Deposit Thus, if a probe comprising a slow neutron detector and Distribution in a Slugcatcher a fast neutron source is moved up and down over the surface of a vessel containing hydrogenous material the detector response provides an indication of the position of the level of the material Interfaces between materials having different hydrogen contents may similarly be detected 3. APPLICATIONS OF SEALED SOURCE TECHNIQUES. 3.1 Onshore and Topsides Applications The gamma-ray absorption technique has been used The gamma-ray absorption technique is also used to widely to determine the extent and magnitude of scale study foaming in separators. Foaming is generally build up in oil pipelines A portable system (Figure 3) combatted by the addition of an anti-foaming agent. is used to survey sections of the line to determine the However, anti-foams are expensive: the correct anti- overall density of the material inside it. Provided that foam must be selected and it must be used at the correct the line is running full (or completely empty) and the oil concentration. The gamma-ray absorption technique density is known, the additional attenuation of the provides a means of directly studying the effect of anti- transmitted signal due to scale thickness may be foam addition The principle of the measurement is estimated. Scale thicknesses can generally be measured illustrated in Figure 5 which shows typical results to within a few millimetres obtained from scans on horizontal vessels The presence of foam above the liquid level modifies the transmission A common use of nucleonic gauges on topsides and profile. Figure 6 shows the results obtained from a onshore installations is the measurement and control of separator with different dosages of a particular anti- interfaces in separators and other vessels. These1 foam. With the higher dosage, the interface is much applications merit further description since the control of sharper and the vapour region less dense, indicating that interfaces can be difficult and radioisotope gauges often the foam is effectively suppressed The ability to study present the only viable solution. the effects of the anti-foam directly and without any disruption to the process is clearly advantageous and Figure 7 shows an instrument arrangement which has can result in significant economic benefits by reducing been used very successfully on oil/water separators. anti-foam usage and optimizing the operation of the separator figure 5. Gamma-Ray Scans of Separators; Principles Figure So Gamma-Roy Transmission Scan Through on empty Figure 7. A Nucleonic Interface Detector Horizontal Vessel for Oil Wafer Separators S«ot«0 dip BottM of vusel tub* 'C«n-r, of *tw«( (auMM P*td I fapafvcwtv Figure Sb Gamma-Ra> tansmission Scan Through Partially Full Horizontal Vessels Figure 6 Gamma-Ray Transmission Scans A radioactive source is inserted into the vessel in a of a Separator to Investigate the Efficiency of AnHfoam Dosage sealed dip tube Usually the tube is inserted horizontally through an available nozzle, though other configurations have also been used The system incorporates a shielded container into which the radioactive source can be withdrawn at such times that vessel entry is required An elongated radiation detector is positioned on the outside of the vessel to receive the radiation from the source. Radiation from the source is attenuated more by the (denser) water than by the oil (Equation 1) so that the detector output signal is a function of the oil/water interface position A portable neutron-backscatter instrument is often used to calibrate the system by providing independent measurements of the interface position. Installed gamma-ray gauges also find extensive use in the control of foaming levels An example is illustrated o s7*.Nce OOVN vr in Figure 8 Figure 8 supplanted by a gamma-ray absorption method, which is Gas compressor protection using a described in Section 3.2. nucleonic level control and alarm ' system 3.2 Sub-sea Applications Vapour ^_. ro compressor f\ The technology used topside is also used below the sea, though of course the design of the equipment is Radioact \.'o!urr>e flowrat* U - Further development of this system which will enable even more accurate tracking of the pig is in hand. Figure 9 The Radiotracer Pulse-Velocity 4. UNSEALED SOURCE TECHNIQUES Technique Unsealed source, or "radiotracer" techniques differ This technique has been used in the offshore oil and gas fundamentally from those involving the use of sealed industry to measure oil, water and gas flowrates For sources of radiation In this instance, radioactive example because of statutory limits on the amount of gas material in a form compatible with the process fluid is which can be flared it is important to measure these injected into the process stream The subsequent flowrates Accordingly, we have measured the flare gas movement of radiolabelled process material through flowrates on many platforms for calibration of installed pipes and process vessels can be monitored using metres and to provide confirmation of the accuracy of strategically positioned radiation detectors. This forms calculation of the tonnages flared. We have also used the the basis of a number of methods for studying mass pulse velocity method to monitor the injection-water transport and fluid dynamics of process systems flowrate in waterfloods The technique can also be used to detect bypass flows and offers a rapid method of 4.1 Flowrate Measurement identifying passing valves Flowrate measurement is one of the most useful 4.2 Residence Time Studies categories of application. There are several ways in which radiotracers can be used to measure flow <5) : The pulse injection of radiotracer also facilitates the arguably the most-useful is that known as the pulse measurements of residence times and residence time velocity technique distribution(fl) If a pulSe of tracer is injected at the inlet to a vessel, a detector mounted on the outlet will The basic arrangement for pulse velocity measurements produce a response curve which is representative of the residence time distribution of elements of fluid in the Catalytic Cracking Units vessel. Analysis of this curve yields important information both about the mean residence time (MRT) The versatility and power of radioactive tracer and the mixing characteristics of the vessel The method technology, as applied to problem solving, is perhaps has been used to study the performance of oil/water nowhere better illustrated than in the study of Fluidised separators. Residence times of oil and water phases are Catalytic Cracking Units (FCCUs) on oil refineries measured separately To perform the measurements, radiation detectors are placed on the inlet pipe and the Fluid Catalytic Cracking is one of the most important oil, and water exit pipes A pulse of organic radiotracer processes on petroleum refineries. The process is used is then injected upstream of the inlet detector and the to convert (upgrade) heavy oils into gasoline and other time of its entry into the vessel is recorded The detector light hydrocarbons The efficient operation of the FCC on the oil exit records the residence time distribution Unit is crucial to successful refinery operations since (RTD) curve Since separation is not perfect, some of small increases in unit efficiency (increased gasoline the tracer also appears at the water exit causing the yield) can lead to very significant increases in revenue. detector located there to respond This procedure is then repeated using a water soluble radiotracer Because of the economic importance of FCCs, they have been the subject of extensive study, both to trouble- Analysis of the residence time distribution curves shoot problems and to optimise operations. permits calculation of the degree of plug flow of the Radioisotope techniques are particularly suited to such two components and also provides measurement of the studies because of their sensitivity, which allows flow- separation occurring in the vessel patterns in large- scale processes to be successfully traced, and because of their unique ability to effectively 4.3 Sub-sea Leak Location visualise the distribution of materials inside operating plant A further application of the use of radiotracers is the location of leaks in sub-sea umbilical cables. Umbilical This paper describes two case studies which are cables between offshore platforms and other illustrative of the many ways in which radioactive tracers installations are essential links covering distances up to have been used to study FCCs 50 kilometres The cables are generally run in bundles contained in an outer sheath Each cable in the bundle 4.4.1. General Principles may be as small as 5mm but a leak on such a cable can be a safety hazard to personnel or the environment and Radiotracers can be used to study the movement and can cause loss of production due to downtime A quick flow distribution of all of the process streams: solid and accurate method of pin-pointing the location of the catalyst, vaporised feed, steam or air. Radioactive leak can save considerable time and money Tracerco material, in an appropriate physical and chemical form is has developed such a technique A piece of radioactive injected into the process material - usually as a sharp gold wire is secured inside a plastic "pig The pig is pulse. In this way, a representative portion of the inserted into one end of the leaking umbilical cable The flowing material is "labelled" with radioactivity and we other end of the cable is sealed and pressure is applied can then follow its movement around the unit using to the insertion end The only fluid movement in the external radiation detectors positioned strategically on umbilical will be towards the leak vessels and pipework As a result of the high sensitivity of modern radiation detectors, the amount of radioactive The pig is carried along the cable by the flowing fluid material injected is small so that the process is not and when it reaches the leak it stops From outside the perturbed or disrupted Nor is there any measurable umbilical bundle a radiation detector mounted on an hazard to plant personal The vaporised feed, steam and ROV monitors the progress of the pig and accurately air flows are commonly traced using gaseous locates the position at which it stops This portion of the radioisotopes Argon-41, Krypton-85 or Krypton-79. umbilical can be brought on board the supply boat and repaired saving the replacement of a costly umbilical The catalyst flow is reliably traced using a sample of the bundle system catalyst which has been irradiated in a nuclear reactor to produce the radioactive isotopes Lanthanum- 4.4 Flow Distribution Studies on Fluidised 140 and/or Sodium 24. Because the catalyst is, in effect gofl its own tracer, the above labelling procedure opens up the possibility of studying the behaviour of different CAIALYST TRACfcH particle-size fractions of catalyst within the unit. 4.4.2 Methodology For the sake of brevity, discussion is restricted to studies on the riser, reactor and stripper sections of the FCC Unit, though it must be pointed out that the technology has been applied with equal success to investigate the performance of other parts of the unit, notably the regenerator and catalyst stand-pipes. Figure 11 Flow up the riser. A typical test arrangement for studies on the reactor, Detector Responses riser and stripper is shown in Figure 10. By measuring the time-separation of the detector responses we can calculate the velocity of the catalyst through different sections of the riser. R C 1,1 nf Jfr.TOfl 1 POTIONS If we subsequently repeat the measurements, this time injecting a pulse of gaseous radiotracer into the feed inlet to the riser (Figure 10), the vapour velocity is measured. Comparison of the results of the two sets of measurements permits the catalyst/vapour slip factor to be determined. The dispersion of the catalyst and vapour can also be measured quantitatively. The responses of the detectors on the riser can usually be modelled by a dispersed plug-flow model and from this, by (for example) computing Inverse Peclet Numbers we can measure the deviation from perfect plug flow. Clearly, by repeating the velocity and dispersion measurements at some future date we have a means of checking the effectiveness of any plant modifications which may have been made to improve the flow characteristics in the riser. 4.4.3 Case Studies The principles and methodology outlined in the Figure 10 Equipment Layout for Radioactive preceding sections can be applied in many ways Some Tracer Studies illustrative examples follow: Tracer is injected as a sharp pulse at appropriate locations and its movement is followed by observing the 4.4.3.1 Flow Maldistribution in the Stripper response of the detectors installed on the unit. Suppose, for example, that it is desired to study the movement of The responses to a pulse injection of catalyst of catalyst up the riser. The labelled catalyst is injected as Detectors D14 - D17, placed at N, S, E and W locations a pulse at the bottom of the riser. The acceleration and around the stripper are shown in Figure 12. dispersion of the catalyst in the riser can be measured by studying the responses of detectors Di - D 4 (Figure 11). 4.4.3.2 Investigation of the Effectiveness of a Riser CATALYST TRACER Termination Device The purpose of the riser termination device is to direct the catalyst flow downwards to the stripper. Ideally, there is total disengagement of vapour from the catalyst: the vapour goes overhead, the catalyst into the stripper bed. In reality, of course, complete separation rarely occurs and, as a result catalyst may be carried overhead in the vapour stream. By studying the results of the radiolabelled catalyst tracer study it was possible to identify a serious deficiency in terminator performance Figure 12 Catalyst Flow Down Stripper. Detector Response Curves Detectors D8 and D9, located neat the top of the reactor (Figure 10) exhibit response curves which are sharply If the catalyst flow down the stripper was uniform, then defined and which contain at least two components the responses of the four detectors would be identical (Figure 14). This, clearly, is not the case and by comparison of the curves we are able to identify excessive catalyst flow in the South quadrant. CATALYST TRACER To investigate the reason for the maldistribution an injection of Krypton-85 was made into the stripping steam ring (Figure 10). The responses of Detectors D14 - D17 of this injection are shown in Figure 13. STRIPP1NQ 6TEAM TRACER Ttut M MCOMOS DCTCCTORS t.1 Figure 14. Investigation of Riser Termination. Response of detectors on the T««C M SCCONO1 OCTECTWS H.li.«.f? Reactor. Figure 13. Steam Flow up the Stripper. The time of arrival of tracer at the detectors, coupled Detector Response Curves with the sharpness of the response curves indicates that a substantial fraction of the catalyst is passing directly up It is obvious that there is a gross maldistribution of the the Vessel. Further weight to this observation is given by steam with a disproportionate amount going up the the response of D10 on the overhead line (Figure 15) North side of the vessel. Presumably, the rapid upflow of steam interferes with the downflow of catalyst - hence, the excessive catalyst flow in the South quadrant From this evidence, it was deducted that the stripping steam ring had suffered damage - a finding which was verified by visual inspection at a subsequent plant shut- down. the oil and gas industry and which will ensure that growth continues in the future CATM.VST TRACER 6. REFERENCES 1. Howell, L.G and Frosch, A ."Detection of radioactive cement in cased wells", Trans. AIME 136 (1940) p 71. 2. Mott, W W And Dempsey J.C., "Review of radiotracer applications in geophysics in the IIMC IM sr.G United States of America", Radioisotopes DCTfCTOn Tracers in Industry and Geophysics, IAEA, Vienna 1967 pp 111 - 131. Figure 15. Investigation of Riser Termination. Response of Detector 3. Priest, MA. "Improved Procedures for on overhead Line. Injecting Radioisotopes During Fracturing Operations", Journal of Petroleum This shows a marked carry-over of catalyst in the Technology, January 1989 pp 46-54. overhead vapour. From these results it was deduced that the termination device was either of ineffective 4. Charlton, J.S , "Radioisotope Techniques for design or was malfunctioning. The device was examined Problem Solving in Industrial Process Plants", at shutdown and was found to be partially dislodged Leonard Hill, Glasgow and London (1986) pp 302-303. Radioisotope technology is a powerful tool for investigating many aspects of the performance of 5. Edmonds, E. A. and Charlton, J.S. "Experience FCCUs. Projects have been carried out world-wide, and in the Use of Radioisotopes, Offshore usage of the technology continues to increase. The Installations and Pipelines", Oil loss Control in development of increasingly sophisticated data the Petroleum Industry, John Wiley and Sons acquisition systems is a key factor in the growth of (1985) pp 199-217 radioactive tracer applications. It is now relatively common to deploy up to thirty detectors on a study thus 6. Guidebook on Radioisotope Tracers in providing a very detailed picture of the fluid dynamics Industry, IAEA, Vienna, (1990) pp 39-101. of the process. 5. CONCLUSION Radioisotope techniques have a generality which makes them of great value throughout the oil and gas industry world-wide. The techniques offer on the one hand a unique window through which the inner workings of production plant can be observed and on the other hand a method of studying the distribution and flow patterns of the process material. These insights into the operating plant, which cannot be obtained in any other way, can realise large savings on continuous production plant by diagnosing faults on line and by providing input data for process optimisation. It is these considerations which have been responsible for the expansion in the usage of radioisotopes within jjag Synchrotron Radiation Application on Protein X-ray Crystallography Palangpon Kongsaeree Department of Chemistry, Faculty of Science, Mahidol University Rama 6 Road, Bangkok 10400 Synchrotron radiation was originally designed for high-energy physics research on elementary particles and very rare occasions on diffraction and spectroscopy research. However, in the last 10-20 years, synchrotron radiation facilities, with high brilliance and rich variety of X-ray beam characteristics, become available for fundamental and applied research in biology, chemistry, and physics. Some of the applications of the synchrotron radiation can be broadly categorized and summarized below: a) Fundamental physics and chemistry Photoabsorption and photoreflection Photoionization Innershell excitation Photoemission Fluorescence and light scattering X-ray diffraction and scattering Topography Circular dichroism Inelastic scattering Infrared spectroscopy UV reflectometry b) X-ray applications Macromolecular crystallography X-ray microscopy Coronary angiography Microtomography small angle X-ray diffraction and scattering X-ray magnetic scattering Surface scattering/ X-ray reflectivity Time-resoved fluorescence Lithography Extended X-ray absorption fine structure (EXAFS) X-ray absorption near-edge structure (XANES) Trace element analysis High-pressure physics etc. Among many applications of synchrotron radiation, more than 30% of the beamlines are devoted to structural biology research, including crystalline and non-crystalline diffraction, spectroscopy and imaging techniques. Instrumentation As high-energy electrons travel in a circular trajectory, synchrotron radiation is emitted. To create a high energy beam, electrons are accelerated in a linear accelerator (LINACX and then transferred into an intermediate circular accelerator (a booster synchrotron), which increases the energy of the electrons to the level of GeV. Consequently, the electrons are injected into a larger storage ring in a high vacuum. A lattice of bending magnets is set up around the storage ring to keep the electrons travelling in a circular path. When the electron beam passes each magnet, the path of the beam is bent, and synchrotron radiation is emitted and can be used in research. SR and macromolecular crystallography Synchrotron radiation has played crucial roles in macromolecular crystallographic research in the past decade. With several unique properties, synchrotron X-ray has several advantages over conventional X-ray sources. Crystals with large unit cells, weakly diffracting or small crystals benefit from the high brilliance; multi-wavelength anomalous dispersion (MAD) benefits from the tunability, and time-resolved studies benefits from the high intensity over a broad bandpass. The role of synchrotron radiation is evident by the fact that more than 60% of the X-ray studies reported in the journals Science, Nature, Cell, and Structure used synchrotron radiation. X-ray crystallography has been proved to be a powerful tool in structural biology to study many cellular components including proteins, enzymes, DNAs, etc. An atomic view of molecular structure yield us better understanding on how these complicated micro- machines function. An analysis of reaction mechanism of an enzyme may yield information crucial for chemists, for the first time, to have a control over Nature by designing a molecule to fit into the active site, and thus inhibiting its function. Hence, structural information in high details is very beneficial on our understanding and high brilliant of synchrotron radiation makes a study at the level of atomic or near-atomic resolution possible with high accuracy. The significance of synchrotron radiation on macromolecular crystallography will be illustrated including recently determined X-ray crystal structures of chorismate mutase and cyclohexadienyl dehydratase enzymes. In the shikimic acid pathway, chorismate mutase catalyzes the [3,3] Claisen rearrangement of chorismic acid to prephenic acid, the first committed step in the biosynthesis of the aromatic amino-acids phenylalanine and tyrosine. The structure of the chorismate mutase domain ofE. coli P-protein complexed with an endo-oxabicyclic inhibitor has been solved for a monoclinic crystal form. The monoclinic crystals form, which belong to space group P2P with a = 83.93, b = 79.40, c = 53.10 A and (3 = 109.08°. The structure has been refined to an R-factor of 19.7% (R-free 26%) at 2.3 A resolution. The r.m.s. deviations for the bond distances and bond angles are 0.008 A and 1.3°, respectively. The catalytic mechanism of the Claisen rearrangement by chorismate mutase will be presented. Also, the evolutionary relationship of chorismate mutase in different organisms will be discussed. N The opportunistic human pathogen Pseudomonas aeruginosa, a Superfamily-B organism, possesses dual pathways in the synthesis of L-phenylalanine. Cyclohexadienyl dehydratase (CDT), encoded by the pheC gene of P. aeruginosa, together with monofunctional chorismate mutase-F (CM-F, EC 5. 4.99. 5), represent an overflow pathway of L-phenylalanine biosynthesis CDT of P. aeruginosa has a broad substrate specificity that gag accommodates both prephenate and arogenate as substrates and converts prephenate to phenylpyruvate or arogenate to L-phenylalanine. The crystal structure of CDT from P. aeruginosa has been determined to 1.8 A resolution using MAD phasing technique. The protein has been crystallized to two different spacegroups with very different crystallization conditions. The enzyme is a homo-trimer in solution. In one crystal form, subunits of the trimer are related by a crystallographic threefold, while in the other crystal form, three crystallographically independent molecules are related by a non-crystallographic threefold. Each subunit folds into two distinct domains separated by a deep cleft, each domain has a common p/ct nucleotide-binding motif. The structure is extremely similar to periplasmic amino acid binding proteins, and amino acid binding sites are also conserved between these two protein classes. The structure and function relationship of CDT will be discussed along with its possible enzymatic catalysis. N "Application of Electron Beam Accelerators for Industry in Thailand" Presented by: Gray Buetzow - RPC Technologies, Inc. Apiluk Lohachitkul - Thai Klinipro Co., Ltd. The presentation will review a brief history on the development of commercial electron beam linear accelerators and the evolution of several of the largest and most important applications. Two interesting new applications for commercial accelerators will be presented and one of the new applications will be highlighted. The presentation will feature and discuss in detail the world's first medium energy, high power commercial accelerator for the sterilization of medical products. This system is installed at Thai Klinipro Co., Ltd. a large manufacturer of disposable medical drapes and gowns. Radiation Therapy The development of linear accelerators for the treatment of cancer began in the early 1950's. The first patient treated for cancer by a linear accelerator occurred at Hammersmith Hospital in London in 1953. Stanford University physicists in 1955 developed the first U.S. linear accelerator and treated a young boy in 1956. Linear accelerators began replacing Cobalt 60 as the preferred method of radiation therapy in the late 1960's. Large multinational corporations began investing in the technology. Siemens, Philips, General Electric, and Varian Associates all introduced product lines of various electron and photon (x-ray) energies. Currently there are over 5,000 systems installed worldwide treating tens of thousands of patients daily. Electron and photon energy ranges for cancer therapy vary from 4 MeV to greater than 20 MeV. The same basic technology developed in the 1950's is still in use today. Modern medical therapy systems are much more reliable and the procedures highly sophisticated. Industrial Inspection Systems Two industrial applications for high energy industrial linear accelerators developed in the U.S. in the late 1960's. Nuclear power plants required thick-walled castings for high temperature water lines and high pressure vessels, each of which required 100% x-ray inspection. Cobalt 60 could be used for thin walled components, but did not have the penetration ability for many of the thick-walled critical nuclear power plan components. Modification and simplification of medical linear accelerators resulted in industrial x-ray systems which generated energies between 2 MeV and 15 MeV x-rays of high intensity. During this same period, the US. Department of Defense was developing a new type of rocket motor. The fuel for this rocket motor was solid like clay and cast in steel or carbon fiber casings. Like any cast material, defects in the solid propellant could form while cooling and these defects needed to be detected. Industrial x-ray film was adapted to meet the needs these new high energy x-ray sources. Varian Associates is the leader in high energy industrial x-ray inspection systems. TWO NEW APPLICATIONS FOR INDUSTRIAL LINEAR ACCELERATORS Two new and very interesting applications are developing for industrial linear accelerators. Cargo Inspection Systems Customs agencies around the world are struggling to keep up with the explosive growth in trade while monitoring goods crossing their border. Most goods are shipped in standardized 20 ft. and 40 ft. shipping containers which offer a fast, safe and secure means of moving large amounts of cargo. Customs agencies, on the other hand, have great difficulty in quickly inspecting the goods shipped in steel boxes. Consequently, smugglers have excellent success in getting their goods into the country with little chance of interdiction. Siemens and British Aerospace were instrumental in developing and demonstrating large x-ray inspection systems which screened cargo containers, trucks, and automobiles. At the heart of this technology is the linear accelerator. Medical computerized tomography technology was adapted for linear accelerator energies and the very large area to be imaged. Containerized cargo is radiographically screened at seaports and trucks/automobiles at border crossings. Fully loaded cargo containers can be screened in a matter of minutes while it may take many hours to unload and manually examine a cargo container's contents. Ten border crossing and sea port and airport inspections systems were sold last year. Electron Beam Sterilization Systems for Medical Disposables Virtually all disposable medical devices must be sterilized after being manufactured and sealed in protective packaging. The limitations of sterilization technologies available dictate that this process be done in large, expensive, centralized facilities. Most manufacturers are required to send their products outside to these contractors, incurring transportation costs as well as time delays of up to two weeks. Currently the two primary methods for sterilizing medical products are: 1) exposing product to radiation emitted by the radioactive isotope cobalt 60; and 2) saturating product with ethylene oxide (EtO) gas. Both of these methods are slow and the gas method is under severe environmental pressures. Linear accelerators generate an intense electron beam which is capable of sterilizing disposable medical products in a matter of seconds as compared to many hours for cobalt 60 and up to ten days for EtO. Electron beam sterilization is an industry accepted method and regulated by national and international agencies. Gamma fCobalt 60) R /T. "a . CI O ) Exposing microorganisms to penetrating radiation has the same terminal sterilization effect as EtO. The product, in its shipping carton, is loaded into a container attached to a conveyor system. The conveyor moves the container into a shielded radiation chamber where it slowly rotates around the isotope. The sterilizing dose is administered based on a pre-selected period of time of exposure. After the dose is administered the container is moved out of the shielded chamber where the product carton is unloaded. Commercial use of cobalt 60 to sterilize disposable medical products began in 1979. Atomic Energy Commission, Ltd. of Canada (now called Nordion International) supplies 80-90% of the world's demand for cobalt 60. Nordion also designs and constructs complete irradiation facilities. As the shift from EtO progresses, medical disposable manufacturers are redesigning their products for conversion to radiation sterilization. Polymer materials manufacturers are developing radiation-resistant resins to expand the number of products that can be irradiated. Although cobalt 60 isotope has become the most dominant method of radiation sterilization, electron beam systems show great potential for growth. Electron Beam The electron beam sterilization process passes an intense, but highly directed, beam of radiation through the medical disposable shipping package or shipping carton which has been placed on a standard conveyor system. Microorganisms are killed by the same total dose as administered by the cobalt 60 method. The biggest difference between the two processes is that a sterilizing dose with an electron beam can be delivered in seconds. Five significant market factors have renewed interest in electron beam sterilization: 1. Increasing costs associated with the EtO gas process and cobalt 60 sources and facilities. 2. Growing public concerns about transportation and disposal of radioactive materials. 3. Serious environmental and cancer-causing concerns associated with EtO. 4. Improved linear accelerator system reliability and serviceability. 5. Greater throughput capabilities. In-line Electron Beam Sterilization System Under the RPC Technologies in-line system concept, the sterilization system is located in the manufacturers' plant where the disposable product is assembled and packaged in the normal fashion. The sterilization process becomes an extension of the production line. A conveyor routes the packaged product through a shielded chamber in which the linear accelerator is located. The product passes beneath the electron beam, receiving a sterilizing dose. RPC Technologies and Molnlycke Health Care created an industrial accelerator product which will meet the industry needs for lower cost sterilization. The benefits of this concept are: • The convenience and speed of sterilizing the product on the factory floor. • Absolute quality control over the complete manufacturing process, including sterilization for those producers now using outside contractors. • No transportation time to and from the contract sterilizer. • No holding time. • Better control of inventory, reducing manufacturing costs. • Very high throughput, meeting the just-in-time manufacturing philosophy. • It is the lowest cost method compared to contract sterilization. Thai Klinipro Co.. Ltd. - Samutprakarn Thai Klinipro is a leading manufacturer of non-woven surgical drapes, gowns, and sleeves. The company is growing rapidly and is expanding manufacturing capacity. Currently the company is distributing its product in Western Europe. After packaging the product, it is placed in shipping cartons where large quantities of cartons are then shipped to Europe for sterilization and distribution. Because the sterilization process was in Europe, it was not economical to return the product to Thailand for distribution and sale. If the product could be sterilized in the factory in Thailand, then all of Southern Asia could become a new market. RPC Technologies and Molnlycke Health Care (a joint venture partner of Thai Klinipro) proposed to install a prototype Minilac® In-line Electron Beam Sterilization System into the factory. The electron beam energy of the Minilac and throughput capabilities would meet the current needs of Thai Klinipro production. The Minilac was installed into the concrete shielded bunker November/December 1997 along with the product conveyor system. The first "beam-on" occurred in December 1997 and sample products were being sterilized by February 1998. This installation is the first medium energy, high power electron beam sterilization system in the world. Technicians who maintain linear accelerators need a knowledge of analog and digital circuitry, microwave components, water circulation systems, physics, and computers. Thai Klinipro maintenance personnel worked on the prototype system prior to installation in the factory as well as participated in the installation and acceptance of the system in the factory. Training of the maintenance personnel was a very high priority because RPC technicians are located in California and if the on site maintenance personnel could not fix a problem, they must have a clear understanding of the system in order to accurately describe the problem over the telephone to RPC field service engineers. Technical Challenges and Problems Installing a prototype system in a factory environment has its technical risks. Thai Klinipro, Molnlycke Health Care, and RPC Technologies felt that the prototype Minilac system, with some upgrades, would meet the performance and reliability requirements of the factory. Continuous system operation has revealed design weaknesses of some subassemblies and components. The microwave source (RF driver) has been replaced with a solid-state subsystem which is more reliable and stable. The electronics which drives the accelerator electron gun has been upgraded to improve reliability and performance. Major systems beyond the linear accelerator also have been upgraded. The product conveyor system needed to have the flexibility to handle packages of several different dimensions including thickness. Mechanical adjustments to the conveyor system between production runs of different product dimensions, need to be made quickly and accurately. Some minor changes to the bar code reading system which tracks products and records system operating parameters have been made Prior to installation, assumptions were made as to what preventive maintenance procedures were to be performed and the frequency of those procedures. Since the operations of the systems, these procedures have been refined and modified. We believe that the preventive maintenance procedures will continue to be modified at least for the next year as we learn more about the system strengths, weaknesses, and procedures. On site maintenance personnel will play a critical role in the refinement of preventive maintenance procedures and ultimately the overall system reliability and performance. Summary Commercial electron beam RF linear accelerators have served very important functions in industry for over thirty years. Radiation treatment of cancer patients and non-destructive testing of thick-walled nuclear power plant components and solid propellant rocket motors have been the primary applications. However, two new applications have emerged which have great potential: cargo inspection systems and electron beam sterilization of disposable medical products. A local Thai disposable medical products manufacturer, Thai Klinipro Co., Ltd., has recently installed the world's first medium energy, high power linear accelerator to sterilize their product in-line on the production floor. The economic advantages of this sterilization concept are enormous and it is believed that in-line sterilization will have worldwide acceptance throughout the medical device industry. TH9900003 TH9900003 DEVELOPMENT OF NUCLEAR INSTRUMENTS IN THAILAND Virul MANGCLAVIRAJ(1) and Suvit PUNNACHAIYA(2) (1) School of Electrical Engineering, Institute of Industrial Technology, Suranaree University of Technology, Nakhon Rachasima 30000, Tel : (044) 224230 Fax : (074) 224220 (2) Department of Nuclear Technology, Faculty of Engineering, Chulalongkorn University, Bangkok 10330, Thailand, Tel : 2186773 Fax : 2186770 ABSTRACTS Realizing the need of nuclear instruments for teaching and research, the development of nuclear equipment was initiated in 1963, a few years after the inception of the Office of Atomic Energy for Peace known shortly as the OAEP. It began with the design of a bench top Single Channel Analyzer (SCA) using electron tubes followed by transistorized survey meter for gamma ray and charged particles monitoring. Modular conceptual design of nuclear instruments was introduced a year later. The dimensions of the bin and modules were designed based on the materials available locally. Bin and various nuclear modules such as single channel analyzer, sealer/counters, pulsers, high voltage supplies, timers and linear ratemeters etc. were developed. In 1965, however, the standard Nuclear Instrument Module or NIM according to USAEC Report TID-20893 was adopted. A great number of nuclear instruments were produced in standard NIM for researchers in OAEP and distributed to universities and other research institutes. Cooperation between OAEP and the department of nuclear Technology (DNT), Chulalongkorn University on the development of nuclear instruments began in 1975. The program was accelerated through research projects and theses assigned to graduate students at the DNT. In addition to standard NIM modules, standard Eurocard modular nuclear instruments were also developed, thus reducing the size and weight of nuclear equipment. This system is known as "mini bin". In 1987, the DNT began the development of computer based multichannel analyzer (MCA). In the past twenty years, several instruments were developed for nuclear researches at the DNT and other research institutes. Besides the research and development of nuclear equipment, the instrumentation group at the DNT is also involved in refurbishing, upgrading, modification and adaptation of existing instruments for specific applications and reuse. High-end technologies in data communication, electronics and digital signal processing will be applied in future nuclear instrumentation development. l. vrrui fonlu llJ 2. 2 n?s;UTUfn5fnijfint4 n (detection) (measurement) .detection measurement detector Amp. PHA r.—* preamp. HV bias radiation detector signal processing and measuring system data analysis Jiirli 3 JIIHIIIJ [l] fl. IS (integral counting system) ifiwfinflfl'JnJJi'injiNfT ;'Wa4^1U (differential counting system) mm imuui uasf-jtion fl. ?SllllT'«l-3mmuTfl0w5lPIUctf (coincidence counting system) 2 |lllllllJ fl0 ]fl1^lTl'i>3lJlJlJnU'34'0? (single unit) ^lu^Yi 2.f1. 0OfllllllJ (modular electronic) (bin) 2.V. fl. single unit 1). modular 3. 30 Tlfut^i [2] 2506 (Single Channel Analyzer; Model 1111 ) it s (desktop) UBS OflfTuiflUlJII^l (rack mount) (Survey Meter, Model 2101) mR/hr ff-3 100 R/hr Dekatron Nixie 3 Single Channel Analyzer Model 1111 4 Survey Meter, Model 2101 lull H.ff. 2507 t V ( modular electronic ) imfuiJVJ (Decade Sealer, Model 1201) (Linear Raicmeter, Model 1501) ^ 5 nas 6 enuami qJ 5 Decade Sealer, Model 1201 %\\r\ 6 Linear Ratcmetcr. Model 1501 worn?) w.pf. 2508 USAEC Report TID-20893 mgYip Standard NIM (Nuclear Instrument Module) [3] «tf-u?uw smj bin) n.n. 2518 f)v^ 7 lias 8 i 2521 u fl9 w (Pulser, Model NT1701) (Training Ratemeter, Model NT 1201) 9 uas 10 S: 9 Pulser Model NT 1701 10 Training Ratemeter, Model NT 1201 4. amnnie"untf .ff. 2523 ua Apple II mtJiime)^nu IBM iilvmimj Iviil w.ft. 2530 Im (MCA) ims;eiln?aI'Ti«uimat)? -. VTA -.V 11 12 Eurocard (survey meter) (dosemeter) (mini sealer) (demonstration set) liaS •WaioK0? (pulser) lufjanil'Ufia'njtynQi'Wfl^fi (pulse pair generator) Q (SCA) imsejiJnianifmsmia'io'Ke-j (MCA) (interfacing unit) 1. (Research and Development) 2. (Upgrading) 3. ow (Adaptation) 4. (Modification) 5. fniihfmiJlJ"l1#l'HiJ (Reuse) 4.1 mi (DSP) 4.2 mimummoiofi504Jj0Yiij0giftjj Imiri mi?nm A 4.4 1 4.5 D I^an liu (PMT) 13 14 NT 2604 15 NT 1802 ^iJ^ 16 NT 1031 5. 5 tl 30% fie y in9 17 fmUn uaswwin uaswmn r\\y\ 17 6. 1. Edition Ten Product Catalog. Canberra Industries, Inc. Meriden, U.S.A. 2. tfitfmiuwawuttamfumemjpffniiieij 30 tl. nd 3. G.F. Knoll. Radiation Detection and Measurement. 2 Ed., John Wiley & Sons, New York, 1989. 4. IAEA-TECDOC-530. Nuclear Electronics Laboratory Manual. International. Atomic Energy Agency, Vienna, 1989. Area Wide Control of Fruit Fly by the Sterile Insect Technique itasintu 8.4 1.8 aruTj rnicru 8 utruH 'CTU 5 (2538 4,882.83 a "I U inn Hfls1tl?llw^W?linJi|lllliSinQil]fls; 17,856.07 aiUUIYl (2540 Ifuvmnibs oijjfni n 17 cfsi Q 0 n 1 ij 1 anternation Atomic Energy Agency: IAEA) ivu ij?jinff ^ijiJ mnvln oiufm vB iiasnii«inai iili4yii4 vlniltlun I141J 2540 w i wouwioiJJ n.ffff. 25282542528-25400 ifimlifiejwinjumTiLly y 22 itvv m utntJ 2525-2533 <»i V 'J 2528 2534-2540 54.7 % uasTuii 2534 wimfnsvh?n?jafi?wvm9 n.i% 4% .linJ 2540 ifliuiYifi m mmi?is?ni'uijfvm 2^30 i l y • i ftflWW\lYll,?\9\l,mi (isolate) wrnim^mi vi.ff 2531 mofipiinjufn? 5,ooo It1 itusii vi.ff 2540 7,000 I?1 2532 vmw\v\l,mm^\}?imttm4i\iHn\un\lw\i}\i\ tje^ v1^YitTii4Us;u'']>3 5,000 li imsil vi.ft 2540 7.000 1? ivunu Vl.ff 2536 1^4^ll^fmsll'^<3lms;'uoy•H^ill9^lvtttf'H3lf1v1^J^ 20,000 i 3/ i 2540 l«lcWJJll40y]fn5WllTJU"31Ull3'U 30,000 li IJ2541 1«11J^1l'UT4lfl1^n1 y • fiiirej-qiviu1 mefi«iiTJUfn? 20,000 1? 6,oooli 9\9cJtD'i^in^ ©iLno^li-a ^vciwi^lviii 20,000 64,000 Ii 2 UVN fig vi :; 20 tfmw-j 10 amfoiiiliJiifiotm ^iingilinyi'g ^vtiflnmji utis jvm ^lj' lfi8fmmwn«qMii^flifiinuNfll^l'51unei8'3i]?5Uitu 5-7 1M (Methyl eugenol)llll4?n'3flO wrfJjrfTS^'lilJJfl^ 11^niJ«nY1TWai7ilJiSU10i 10-20 flU 7 5i4 U'I MIBT? l^fffi^BCViflTiCacetone techrique) ivu 82 % ii£isna>ifnnfniiJEi88li4i]ii?nyiijfn7viitn8m^8 30.3 2541 2. tj 2531 nufn?>ii?nfj 59.2% 2541 wufmThsno 1.4 3. liiil 2 31.9% ii3sivunulviiJ254i 2527 54.7% unslull 2541 7.4% 100 <••• so \ 60 40 20 • • • -B \*~ ^^^-^ * ; 3-^ ==« 0 ~1 1 —r— 1 —-A1 r~. -f ir 253 0 253 1 253 2 253 3 253 4 253 5 253 6 253 8 n ?54 1 So® Social Advantage on the Peaceful Use of Nuclear Energy by Yoshio Murao Director, Nuclear Technology and Education Center, Japan Atomic Energy Research Institute, Tokyo, Japan ua~msinwis ....A B D iia~msmwis (A) TH9900004 TH9900004 •uiiyem tfiun-nunaisfmiifmBivmuastn 1m. 5907273-4 2/nf)«Yiinflnrrwfibn'm m 1m. 5795230 fie 581 ti^TiWfiv 1m. 5899850 ^0 9065 o In?. 5899850 WB 9056 nloo . 152-2539) 2.5 n 90 1 log cycle 7.5 nlamiu 1,000 12 iwau 10 nTmnso m5!i Reducing Microbial Contamination in Herbal Cosmetics and Raw Materials from Natural Source by Gamma Radiation Yupa Tiengthavaj, Suwimol Jetawattana , Kwanyune Sripaoraya , Suwanna Charunuch , Phongpraphan Susanthitapong 1/Cosmetics Control Division, The Food and Drug Administration Tel. 5907273 2/Biological Science Division, Office of Atomic Energy for Peace Tel. 5795230 ext 581 3/Toxicology and Environmental Laboratory, National Institute of Health, Department of Medical Sciences Tel 5899850 ext 9065 4/Division of Cosmetics and Hazardous Substances, Department of Medical Sciences Tel 5899850 ext 9056 ABSTRACT Six kinds of natural cosmetic raw material powder (Zedoary, Siamese rough bush, soft chalk mixtured, tuberous plant, cuttle-fish bones, creat) and five of herbal cosmetics (facial scrub powder, facial wash powder, tooth powder) were studied. Samples were irradiated in dry state by gamma radiation and kept to investigate microbial quality for twelve months. Minimum dose of 2.5 kilogray can reduce the exceed number of microbial loads in some samples at least 90 % or 1 log cycle from the beginning. The dose at least 7.5 kilogray can diminish the exceeded 1,000 colony/gram of contamination in all samples to the desired level. No change in number of survivors during storage were detected. No skin irritation effects were observed up to 10 kilogray and major physicochemical properties (pH and color) were not significantly changed in all samples except tooth powder. l. nun iiiJ^wf«THT4n milVmui vifomm nm uifuymssHU filuinflwu iflaaiwiin vweinijj wvi m vi. ff. 2535 9 (w. ff. 2536)(2) 152-2539)<4) yn-j ivu \nntT 1jJSuinumiuiJi5iJiil'Ujji«ifiiw Miaun5iojjfmjJifnuiiHV4lunoj iifuuais'Huniia-jfmiJunjauflauYiso arm v iiiitiJjiiiiila-jnumiiJuiilaurnnfnawanifi' nJimu a f vnn (2537) 51 flioein waiifins'Hvn-j^aSiQVifJiviii'ii uCfiw-) 25 pfiam^ Iiimuieiii'm 23 (85.19%) filulavu/ifla 13 w'J9m^ljji'uiJJi«?siii 2 ehatin (15.38%) tfylvlaj 11 en 9 tin m v (3) 1914 Antoni (1973), Armbrust Uf\t Laren (1975) lias Jacobs (1984) biomaterial Reid lias Wilson (1993)lflinflni1 'Ulllll'UncnUTUMcnfJlluPI') Preservatives 'Uetia^'Hia llJ itTiafJ D-3'Vni'Hfl0-3Umifnilfl3Jfn5li)iqjl^lim 6-9 io4 tnua (2538b) 1piffnwini5ViiaioBawYi1olut)iiiwi4liin«u«ioi^minjjui iwmnwuiunfu^i 6 ibsifivi Ifiuti tniStn mwau OTUIJ oi^nniaulu oin^o ua nn n 90 iiJaiWua vtla l leg cycle 6.82 nlainio MiajjifiniiPinflwiJ^aiiviitfiiiyjnwiatinljjinu l.oooifiiawnijj vrfe 4i A d (uan. 152-2539) iw •Huion-3 1 log cycle 90 % 2. 1. (Quasi experiment) flllJfjU exposure 1^1 (Non-probability sampling) eh a tin If) en Is vi (Criteria) lumi 2. 2.1 niMVIfl'HMIlflfU'yf (Criteria) 2.1.1 ^f 2.1.2 2.2 ilfmmuehednfliw I (1fia?hiJn-ni4fifus:fm3jfm9iMiiiiastn) 2.2.1 llcl i flntn uibitlufliilum end (l) ?iijvliii40fjn'ii looo niu (fliuiu 5 wiam (2) V fiT»i4j;^iniJ0m^}Jiiii-a1pfq^ncii?T^n^as;0i^ ^HiflfJifiiouiiJ nmz 100 niw uns; 900 fnu wo l ^Q0fii^ uaiilfiiJinn^^ioniiSa (Seal) ^leifmufgu (fliuiy 6 ^i 2.3 uu^^gfJi-JBgniiliJ 2 pfiu eriw^ l iJfjjifliwigm-jiu'nifji^tr 9EJi-jas;il?s;jJifu loo niu ff^ fntT^ifiilimVIO m9«nyilJ?U1«JBH JJ0D. 152-2539 2 lJi3J1tU^10EJ1-3 0fJ1-3asiJiS}JlfU 900 fill) ^iMtt polyethylene O^ 25 fifw uaiwufiilino^i'Hft'uyi \ji1il«ifjf^^^il?3Jiflj 2.5 ,5.0, 7.5, 10.0 nlainio (uas 25.0 Gammacell model GC220 aemfmilHftff (dose rate) 13.11 PllfJ Radiochromic film FWT-60-00 01UfhfniUl\m 605 nm. d " " 2.4 muniiwiafJU'Ki flf^^ 2 uas 3 200 nfu ff^tfiiTn^iuvia^^iTJiJiJJiflimQnviw me 3. nw 5 wf\ wim io3 - io6 flfjjJ Bacillus SlWEH 3 fll9EJ"l-3fl9 1J9EJ1JA ITUUHfh Uf\Zftl}\l\vi13t\)f\WU~\ I presumptive coliform ifVUinfllijTUfhM'Ufl niiQiEJi^^iJ?3JiQjadi-3'U9fj 2.5 niamio d 90% MID l log cycle l log cycle 2.5 v spore forming bacteria 111 114in^« 19til-3 iiJVI MUUQm 1J9EJ 2.5 nlniniOl3wwi\4ilJ«i;iiilMRnfl1jivilJ presumptive coliform ijJinu 1,000 Ifilnfi«8fiijj?njj^inwisii4«8^fni iiPisiJfuiful'^CTedi^'ueti 7.5 nininiy Swa 1,000 ifila'u^eniwlu'vifi^am^cififi^jJiaEil'ui^^iuiu'm'u 1,000 7.5 0^ 10 filninifjflK'nilMfinflwui?9li4«i8di^1iJinw 10 2.5, 5.0, 7.5 ims; 10 3,6,9 lias 12 10 if iiw 2.5 nimmo if ma^me^W' (test of primary irratation) (a inn 5.0,10 ims 25 n n vtiu V V VXt 'M^Sl1Ua-33J1i)in^iam-311-3'HJJfl9Ei1lJ?TflTH dry state Uflsetflum'inJSllfl S-3 "w'wm5llu 3 wla 6 panel aeJi^^afj 10 10 niainia (wan. 152-2539) ss ^ loo 10 fi iliintuini Miafmunw iiluw io3-io6 7.5 nlninifl' SwflTiii'HiliJJifu^uviioiJuitlauinu 1,000 (wan. 152-2539) (wan. 152-2539) iiu H-JHIIO (Talcum) 10 3 2. 3. uns mwu? Ififi lfiiuwafififucviviuf3«jfnvi UHS Gammaceil-220 5111 6. . (2536). 1 Cw. pf. 2536) 119-3 2. nis;inn-3insi?ojtT6u. (2536). 9 (w. fl. 2536) ifg-3 v\. ft. 2535 3. T'u. (2537). gwa^in aim inn 4. ttiyn-3iy3Ji^i§Tuwa?inflj(:ng¥i?nMfiii}j (2539) h . 152-2539 11 5. ?TTun^ivsjJiPif5TV4wH«nfucn9^invrn??jj (2525). fl!0"U : Ulk^U JJQfi. 443-2525 6. fpua [\l9\tl 8. Antoni, F (1973). Manual on radiation sterilization of medical and biological materials, Technical Reports Series No 149, International Atomic Energy Agency(IAEA). Vienna. P. 13 9. Armbrust, R. F. and Laren, N. H. (1975). Radiopasteurization in the processing of non sterile pharmaceutical preparation and basic material. In radiosterilization of medical products 1974 (Proc. Sym. Bombay, Dec. 9-13, 1974), IAEA, Vienna. P. 379-382 10. Jacobs, G. P. (1984). In cosmetic and drug preservation : Principles and practice (edited by J. J. Kabara), Marcel Dekker, New York. P. 223-333 11. Reid, B. D. and Wilson, B. K. (1993). Radiation processing technology for cosmetic : A report on a Canadian study. Radiat. Phys. Chem. 42(4-6):595-596. 12 ehaun Total colony Presumptive Pathogenic bacteria' Skin count coliform and Fault producing irritation 3 (<1000CFU/g) (<10/g) organisms 1.75 x 106 <10 IJJVUJ linSflitHflB^ niao 4.39 x 10" 2.4 x 103 IWWJ luiSfiltliflB'J 3.65 x 105 <10 1.50 x 105 1.15 x 102 Iiiviu l.lOx 105 <10 "liivm 3.76 x 106 <10 ID'VIU luisfiitiifia-i 4.10 x 103 <10 Iiivcu 8.40 x 105 2.2 xlO2 ljju;fnfjifia-3 7.25 x 103 <10 IJJ'VIII 6.62 x 106 <10 lu'vm 8.00 x 10! liiviu wan. 152-2539 (Faecal coli, Staphylococcus aureus, Pseudomonas aeruginosa, Salmonella spp.) {Closthdium 100 niu 13 (kGy) 0.0 2.5 5.0 7.5 10.0 1.75x10 8.55x10 2.20x10 4.39 x 104 2.21 x 104 7.35 x 102 3.65 xlO5 2.09 x 104 6.75 x 102 1.5OxlO5 <10 <10 aunna l.iOxio5 s.iOxio3 i.i6xio3 3.76 x 106 6.69 x 103 3.40 x 103 4.10 x 103 I 8.40 x 105 9.25 x 104 6.65 x 103 II 7.25 x 103 <10 <10 II 6.62 x 106 1.09 x 105 8.60 x 103 II 8.00 x 103 (CFU/g) 14 pH lOkGy 6.34 6.32 1)00 6.35 6.23 6.40 6.35 6.68 6.45 7.43 7.51 7.90 7.83 8.54 8.70 5.82 5.44 8.53 8.53 II 6.39 6.76 II 4.04 3.15 15 LL o o 2.5 5 7.5 10 Radiation dose (kGy) LL o 81 2.5 5 7.5 10 Radiation dose (kGy) B:iJ9t), C: 16 unz M. E.A ingles umfi'lulamm^i8i5tJ IIVJUBITI 12120 1m. 524-5476 TviJPni 524-6200 NPI ims c e nuu MA 1-uti^iAiaitTwn PVNP »-jSiJiiJifUfniu0ij1pi9Ofi1 Bfl 20% uaslulwiiuu 80% mu 5 °C ntantn 8 ^iJflTH mOMyBKQfittmi^^fniUl^U 1 kGy lias 2, 4 kGy a^ncwifni^nfltToiJ'yjn «I1PITH u 40 luufus;^ MAP 44 iu mQMjjyiuii^'fauuu^ysyifnfmfls MAP uaswiiJfniQiof^ft l kGy fls 48 i^niQn^uti^i'uti^ NPI itas; PVNP Senqmiinuimn 8 kGy B^SQiymitnuirnnunnfiQi 8 ^d?nw fhusniBEh-a'tflfmefm'vnut^fl 4 kGy u 2 m™i)3flioth^'UJ''l&ntif'-afl TH9900005 TH9900005 17 Quality Evaluation of Meat Products in Relation To Packaging and Irradiation Athapol Noomhorm and M. E.A Ingles Agricultural and Food Engineering Program, Asian Institute of Technology, Pathumthani, Thailand 12120 ABSTRACT The effects of low-dose radiation (<10 kGy) were evaluated based on the changes in the quality of meat products and the performance of films used. Fresh pork sirloin meat and smoked sausages were vacuum-packed in NPI pouches and modified atmosphere packed PVNP films with 20% CO2 and 80% N2 gas and stored at 5°C for eight weeks. Fresh samples were irradiated with I kGy while smoked sausages were irradiated to 2 and 4 kGy doses. Quality evaluation were conducted every week. Mechanical properties of films were determined at the start and at the end of the storage period. Vacuum alone extended the shelf life of fresh meat to 40 days while MAP to 44 days. Vacuum packaging or MAP with 1 kGy made meat still acceptable up to the 48th day. Packaging system with NPI and PVNP were able to protect sausages against deterioration for 8 weeks. While two kGy with vacuum and MAP extended the storage life of sausages for more than the eight weeks of storage, 4 kGy dose can double the shelf life of unirradiated samples. Sensory tests showed no effects on the acceptability of the irradiated products. Tensile and tear strength of all films used decreased after storage period. Irradiation did not significantly affect these properties of film, transmission rates for gas and water vapor through NPI and PVNP. 18 INTRODUCTION Good manufacturing practices (GMP) is one of the backbones in the food industry. With the numerous reported cases of food-borne diseases, various areas in food manufacturing are given emphasis. Because processing poses possibilities of bacterial contamination, new methods of packaging have been developed to counter the threats. Modifying the existing atmosphere of the packaging by removal of gases (vacuum packaging) was found to preserve the color characteristics of food materials, decrease rates of oxidation and spoilage (Newton and Rigg, 1979; Lynch et al., 1986), maintain product quality (Ho et al., 1995) and extend the storage life of fresh meat (Rousset and Renerre, 1991) while flushing specified amounts of oxygen, nitrogen, carbon monoxide and/or other inert gases was reported by Young et al. (1988) to inhibit enzymatic spoilage. In particular, Gill and Harrison (1989) discovered the effectiveness of carbon dioxide against spoilage and pathogenic bacteria. Aside from extending the shelf life, safety of food consumption is ensured. In any packaging system, the performance of the packaging materials used has the most critical role as they are responsible in the protection of the products inside against abuses and microbial contamination (Pszczola, 1995). The thickness and the strength of the films ensure the protection of the product from physical and mechanical damages. As meat products are stored in low temperature and high humidity areas, the permeability of the materials against water vapor would assist in preventing the entry of moisture. Particularly for MA-packed produce, the permeability of films to gas is important in regulating the gases inside the pouches. Nonetheless, microbial activity will soon overcome the effects of packaging and proceed to degrade meat tissues. Elimination or reduction of spoilage and pathogenic microorganisms at the start of storage would further assure the extension of shelf life and the safety of meat. Application of ionizing radiation is efficient in removing the microorganisms present (Brody, 1996). Irradiation at low-doses (<10 kGy) was found to eradicate and inhibit the activity of pathogenic bacteria, like Salmonella (Noochpramul and Loaharanu, 1974). Although total microbial count decreased with increasing radiation dose, organoleptic changes observed at higher doses may affect consumer acceptability (Lacroix, 1995). A radiation dose of 3 kGy was found to reduce the population as well as preserve the sensory attributes of meat products. 19 Although significant studies have been conducted on the effects of irradiation on food materials, very few has dealt on its effects on the performance of packaging films. It should be considered that these materials come in contact with the food and any changes in their properties may significantly instigate unfavorable changes in the quality, shelf life and safety of food. It is this light that this paper aims to determine the changes in the quality of meat products: fresh and processed meat and the performance of the packaging films used as influenced by the packaging method and irradiation dose. MATERIALS AND METHODS An experiment conducted by Maneesin (1995) showed that compatibility of packaging method and materials contribute to the effectiveness of packaging system. The study found out that of the packaging materials used in the meat industry, laminated films of nylons were better compared to the usual polyethylene pouches. In particular, laminated film of nylon and polyethylene with ionomer resin (NPI) was found to be best in combination with vacuum packaging due to the sealing properties of ionomer resin and nylon. It also has good permeability properties. Also, laminated film of polyvinyledene chloride-coated nylon and polyethylene (PVNP) was most compatible with modified atmosphere packaging due to its thickness and its ability to restrict the movement of gases. Based on these results, the above films were utilized for this experiment. Sampling and Packaging Procedures Fresh sirloin cuts were obtained from Freshmeat Processing Co., Ltd., Nakorn Pathom Province, Thailand on the day of slaughter. Smoked sausages were purchased from C.P. Interfood (Thailand) Co., Ltd., Samutprakarn Province, Thailand. Fresh meat samples were cut in 2 i 0.5 cm thickness and packed in conventional method with stretchable films and plastic trays, vacuum-packed in NPI plastic pouches at 90 psi and modified atmosphere-packed in PVNP pouches with 20% CO2 and 80% N2. Smoked sausages were packed at 100-gram per pack in vacuum and modified atmosphere packaging using NPI and PVNP. All control samples were packed in low density polyethylene (LDPE) films. 20 Radiation Treatment and Storage The y-irradiation source was Cobalt using Gammacell 220 facility (Nordion International Inc., Kanata, Ontario, Canada). With a dose rate of 0.22 kGy/min, fresh samples were treated with 0 and 1 kGy while smoked sausages at doses 0, 2 and 4 kGy. Storage condition for all samples was 5 i 2 °C. Changes in the microbial population present, acidity and pH levels, texture and color attributes and sensory scores were evaluated every week while the performance of the packaging films was assessed at the start and the end of each storage period. Microbial Population Following the steps outlined by DiLielo (1982), bacterial count was obtained using decimal dilution and total plate count method. A maximum bacterial density of logl0 7.0 cfu/gm was used as deciding factor for spoilage (Kraft, 1986: Molins et al., 1991: Brewer et al., 1994). Physical and Chemical Properties The moisture content of the meat samples was determined using CEM methods (AOAC, 1984). Fat extraction was made with 70 ml hexane as the extracting agent at 120 °C for 5 hours. The differences in the weights after the first and second drying process were used to compute the moisture and fat contents of the meat samples. Ten grams of samples were blended with 90 ml distilled water for 1 minute. The slurry produced was then utilized to measure the pH which was recorded within two minutes after slurry production. Samples of meat products were weighed at the start and at the end of storage to the nearest 0.001 gram. The differences in the weights were used to calculate the percentage drip loss (Seideman et al., 1979). Appearance, particularly color, is one of the major deciding factors used by consumers in determining the acceptability of meat products (Jeremiah and Greer, 1982; Molins et al., 1991). Color attributes expressed in the changes of the values of 'L' (lightness-darkness), 'a' (redness- greenness), and 'b' (yellowness-blueness) were monitored every week from the start of storage. A modified procedure used by Bourne (1978) was employed to evaluate the hardness of the meat and meat products using the Instron Universal Testing Machine (UTM) with Kramer 21 Shear cells having a cross head and chart speeds of 50mm/min and 200 mm/min, respectively and a maximum load of 500 kg. Eight panelists aged between 28-40 years old were asked to assess the color, odor and overall acceptability of the fresh meat and meat product in an eight-point scale with eight as the highest score. Smoked sausages were boiled for 5 minutes before serving. Film Properties The films were evaluated in terms of thickness using the average of ten readings (to the nearest 0.0025 mm), tear and tensile strengths following procedures outlined by ASTM D1922-93 (ASTM, 1993) and ASTM D882-91 (ASTM, 1991), respectively and transmission rates of water vapor and gas through the films by ASTM D1434-82 (ASTM, 1982). Conditioning of films was made at 27 C and 65% RH for at least 48 hours prior to film property determination. Statistical Analysis Analysis of Variance (ANOVA) was used to analyze all gathered information with Least Square Difference and Duncan's Multiple Range Test (DMRT) to differentiate the means. RESULTS AND DISCUSSION Microbial Population Generally, after slaughter, fresh meat contains around log|0 5.0 cfu/gm. Due to this high count, the usual shelf life is between 3 to 5 days. With log10 7.0 as the maximum bacterial density for termination of storage period (Thayer et al., 1995), vacuum packaging was found to preserve fresh meat samples for 40 days, twice the life of those packed in plastic trays and flexible films. Modifying the atmosphere by flushing 20% CO2 and 80% N2, resulted in a shelf life of 44 days. Enfors et al. (1979) supported this result emphasizing the bacteriostatic effects of CO2 and later confirmed by Gill and Harrison (1989). Probably due to the low-dose (1 kGy) applied no pronounced differences were observed after the application of irradiation (Tables 1). The smoked sausages in LDPE vacuum and MA pouches unexposed to irradiation were found to be stable until the fifth week while those in NIP films displayed storage stability until eighth week (Table 2). Unlike the fresh meat, irradiation was effective in reducing the microbial 22 population present in smoked sausages. A reduction of 28.46% and 68.79% was observed upon the application of 2 kGy in vacuum- and MA-packed smoked sausages, respectively while a decrease of 71.12% and 68.79% was found in vacuum- and MA-packed samples with 4 kGy dose, respectively. Physical and Chemical Properties of Meat Products Both the fresh meat and smoked sausage samples showed no significant changes in the moisture content. The slight increase in the fat contents of the smoked sausages was found due to the sensitivity of lipids to irradiation treatment. This phenomenon was supported by the report of Desrosier (1970). Although reports revealed the formation of off-odors upon the application of irradiation (Blumenthal, 1997), no such reactions were observed during the experiment. The changes in the acidity of the samples determine the rate of degradation by enzymatic and microbial reactions. Normally, the pH of meat after slaughter is between 6.4 to 7.0 (Rosset, 1982), but because meat would continue to undergo physiological reactions, pH levels changed with storage time. In this experiment, all samples, regardless of packaging method and irradiation dose, pH levels decreased, although irradiated samples proceeded to a slower rate. In the like manner, the weights of samples changed with storage period as a result of movement of water from the inner tissue to the surface as affected by humidity and temperature. Of the packaging methods, vacuum packaging was found to cause a greater loss in exudate than MAP (Seideman et al., 1979 and Lawrie, 1983). Fresh sirloin cuts had percentage drip loss of around 3.93% to 11.32% with the samples packed in flexible films having the highest loss. This may be caused by the difference in the type of packaging material and the absence of proper sealing of the flexible film. Between vacuum packaging and MAP, the former resulted in higher loss due to the shrinkage of film and product as the gases inside the package were removed. The same results were observed with the processed meat. Smoked sausages in vacuo with LDPE films exhibited the greatest loss at 2.87%, but the application of irradiation decreased the rate of water loss in the sausages. 23 Table 1 Microbial population in fresh meat samples, log10 cfu/gm. t 0 4.2553 4.2788 2.6021 4.1461 ND 4 4.8633 4.7243 2.9685 4.2553 ND 8 5.9243 5.0000 2.8451 4.7709 ND 12 5.9191 4.8451 3.2040 5.2041 2.4624 16 5.9445 5.2553 4.3802 5.0414 3.6811 20 6.3424 5.3424 4.6128 5.3010 3.7709 24 7.2304 5.3979 4.5798 5.4771 3.8921 28 - 5.4624 4.8261 5.6335 3.9685 32 - 5.9345 4.9085 5.7634 4.2041 36 - 6.6232 5.0414 5.9030 5.1139 40 - 6.9685 4.3424 6.3222 5.3222 44 - 7.0792 5.7324 6.8921 5.9912 48 - - 6.4914 7.3617 6.7853 ' ND - Not detectable Table 2 Microbial population in smoked sausages, log,0 cfu/gm Weeks in WPBO PW4 3.5682 3.4624 2.4771 1.0000 3.1461 3.2041 ND ND 4.6901 3.7559 2.7160 1.4771 3.8692 3.3010 ND ND 4.8388 4.3979 3.2041 1.7782 4.9191 4.0792 2.2041 ND 5.2304 4.6532 3.2532 2.3979 5.2553 4.5798 2.7782 ND 5.8633 4.7160 3.5441 2.4771 5.9777 4.7782 3.0414 ND 6.6335 5.5979 4.5139 2.6532 6.5911 5.3802 3.6721 ND 7.3451 5.8624 5.3010 2.7160 7.2947 5.9243 4.3802 2.4314 5.9121 5.5051 2.6021 5.9956 4.6902 2.3979 6.2928 5.5315 3.0792 6.5315 5.0414 2.4914 ' ND - Not detectable 24 As gathered by Brewer et al. (1994), vacuum packaging was the best method in preserving the color characteristics of the meat samples. Fresh meat samples packed in vacuum showed good color retention and the application of 1 kGy made the color attributes stable throughout the storage period. Smoked sausages in LDPE pouches both in vacuum and modified atmosphere had lesser degrees of redness ('a' values) as compared with the other treatments. Packing in vacuum produced a more stable color quality than MAP while application of irradiation with 2 and 4 kGy created some fluctuations in the intensity of the different color attributes. In the MA packages, exposure to 2 kGy produced sausages with lighter color than other samples. The texture characteristics of the meat products, on the other hand, were behaving in accordance with the results obtained by Berry and Leddy (1984) and Matulis et al. (1994) which said that the resistance of meat products to force is directly proportional to the fat content. Because the fat content in the meat samples did not vary much, degree of hardness was not significant among treatments. For the sensory evaluation, it was also found out that vacuum-packed fresh meat slices were preferred over MA-packaged ones. The production of off-odors, particularly in unirradiated ones was attributed to the presence of bacteria emphasizing the impact of radiation in the elimination or reduction of microbial population causing degradation and spoilage. For the smoked sausages, vacuum-packed samples were more stable than those in MA pouches in terms of color attributes. Irradiated samples, although there were slight changes in the color characteristics, were preferred by most of the panel members, particularly during the later part of the storage period. Film Properties The properties of the films used were tested based on their tear and tensile strengths, thickness and gas and water vapor transmission rates. Tests showed distinct variations in the initial and final properties of each film (Tables 3 and 4). Elongation and tear strengths of fresh meat varied with direction: longer elongation was observed with samples cut in machine direction (MD) than in cross direction (CD). While opposite trend was detected in case of sausage samples. Tensile strengths of both products provided higher value in CD direction. Permeability, expressed in transmission rates, varied with type of packaging materials. Among the film used, PVNP exhibited the least gas permeability with oxygen transmission rate at 3.65 m /m -day, followed by NPI with 5.77 m/m-day, LDPE with 6.05 m An -day and flexible film with 11.76 m /m -day. These differences were influenced by the various properties of films laminated together to form these 25 packaging materials, like nylon which is stable in high temperatures and is reported impermeable to gas. Polyethylene film is soft and flexible but water impermeable (Hanlon, 1984). Whereas ionomer resin is heat stable and chemically inert, nylon with polyethylene is highly resistant to grease, oil, water vapor and gas. At the end of the storage period when films were exposed to low temperatures and high humidity, all underwent changes. Tensile strengths reduced as well as elongation and tear strengths. Transmission rates increased due to the exposure of films to high humidity conditions (Rigg, 1979; Lambden et al., 1985). The application of irradiation reduced the film permeability but this change was not significant as indicated by statistical analysis. These results showed that the high-energy produced during radiation process did not affect film performance which coincided with Desrosier's experiment (1970) reported that irradiation has no effect on packaging materials at doses below 20 kGy. t-0 Table 3 Properties of packaging materials used in fresh meat samples Control in flexible fflm vmawHftKasteta m MAPinPVNP F9m Properties fnitul Final FaatCeai&K *#• Edition Condition Condkkm OkGy JkGy Cowftw ikGy Thickness, mm 0.010 0.012 0.076 0.075 0.075 0.089 0.088 0.089 Tensile Strength, kg/m cross direction 469.86 317.73 561.88 480.95 461.27 420.79 415.95 399.82 machine direction 354.17 273.64 423.53 416.67 394.91 459.51 414.09 397.06 Elongation, mm cross direction 23.95 15.21 37.43 26.67 25.00 36.67 41.67 33.33 machine direction 40.44 25.63 63.33 65.00 56.67 38.33 55.00 37.50 Tear Resistance, gm cross direction 408.00 371.50 32.00 39.00 34.66 72.00 86.00 88.00 machine direction 512.00 466.25 37.42 42.38 35.25 78.88 83.00 96.00 Transmission Rates Water vapor, 60.72 102.24 19.68 20.60 16.72 5.28 8.08 4.56 g/m"/day Oxygen, m /m'/day 11.76 16.44 5.77 8.34 5.66 3.65 7.81 5.94 Table 4 Properties of packaging material used in smoked sausages Vacuum Patftggng ModiM AttKMpbere Padogmg LDPE m U PVNP Film Initial Final MM Recondition Initial m Fmal Condition **.. «-<. . CaamoB Properties condition Coalition OfcGy 4feGy OkGy 2kGy 2kGy VOHSSOD <. 4bGy Thickness, mm 0.0530 0.061 0.076 0.075 0.075 0.076 0.053 0.056 0.089 0.089 0.09 0.09 Tensile Strength, kg/m2 cross direction 235.76 204.70 561.88 504.55 508.75 508.15 235.76 207.88 420.79 397.23 388.70 396.90 machine direction 206.29 183.97 423.53 390.39 369.26 369.43 206.29 181.03 459.51 432.70 398.50 405.10 Elongation, mm cross direction 313.33 383.33 37.43 31.67 33.33 30.54 313.33 275.00 36.67 40.00 40.00 36.67 machine direction 182.96 220.00 63.33 65.00 51.67 55.00 182.96 163.33 38.33 33.33 35.00 31.67 Tear Resistance, gm cross direction 980.50 950.48 32.00 30.50 32.00 31.88 980.50 960.00 72.00 82.32 82.00 95.36 machine direction 856.25 830.00 37.42 33.34 32.38 34.86 856.25 842.88 78.88 86.64 83.36 86.32 Transmission Rates Water vapor, g/m /day 4.320 6.040 19.680 23.040 15.480 12.880 4.320 7.200 5.280 5.760 4.92 3.84 Oxygen, m An /day 6.05 7.140 5.77 7.51 7.28 6.87 6.05 7.189 3.65 7.477 5.14 4.74 to 28 CONCLUSIONS 1. Between vacuum packaging and modified atmosphere packaging, the latter was effective in preventing the loss of water in the meat products and extending the shelf life by inhibiting the growth of microorganism. 2. Irradiation was efficient in reducing the microbial population in meat products: reduction of 28.46% and 68.79% in smoked sausages treated with 2 kGy in vacuum- and MA-packaging, respectively, 71.12% and 68.79% decrease in vacuum- and MA-packed samples with 4 kGy dose. 3. Packaging and irradiation did not significantly affect the moisture, fat content and the texture characteristics of the fresh meat and smoked sausages. Both were not effective in inhibiting the decrease of the levels of acidity of the sample, though irradiation slowed the rate of decrease. 5. The exposure of films to low temperature, high humidity storage resulted in lower tensile strength and elongation, but slightly increase the permeability to water vapor and gas. 6. Irradiation decreased the transmission rates of gas and water vapor through the packaging films as well as the tensile and tear strengths and the elongation but all of the changes were not significant. REFERENCES AOAC. 1984. Official Methods of Analysis. 14th ed. Association of Official Analytical Chemists, Washington D.C., USA. ASTM. 1991. Standard Test Methods for Tensile Properties of Thin Plastic Sheeting Reference No. D882-91. American Society for Testing and Materials. ASTM. 1982. Standard Test Method for Determining the waster vapor transmission rate—Dish Method Reference No. D1434-82. American Society for Testing and Materials. ASTM. 1993. Standard Method of Test for Propagation Tear Resistance of plastic film and Thin Sheeting Reference No. D1922-1993. American Society for Testing and Materials. Berry, B.W. and Leddy, K.F. 1984. Effects of fat level and cooking method on sensory and textural properties of ground beef patties. Journal of Food Science 49:870-876. Blumenthal, M.M. 1997. How food packaging affects food flavor. Food Technology. 51(l):71-74. Bourne, M.C. 1978. Texture profile analysis. Food Technology 32(7):62-66. 29 Brewer, M.S., Field, R.A., Ray, B. And Wu, S. 1994. Carbon monoxide effects on color and microbial counts of vacuum-packaged fresh beef steaks in refrigerated storage. Journal of Food Quality 77:231-244. Brody, A.L. 1996. Integrating aseptic and modified atmosphere packaging to fulfill a vision of tomorrow. Food Technology 50(4):56-66. Desrosier, N.W. 1970. The Technology of Food Preservation. AVI Publishing CO., Inc. Westport, Connecticut. DiLielo, L.R. 1982. Methods in food and dairy microbiology. AVI Publishing Co., Inc., Westport, Connecticut. Enfors, S.O., Molin, G. and Ternstorm, A. 1979. Effect of packaging carbon dioxide, nitrogen or air on the microbial flora stored at 4°C. Journal of Applied Bacteriology 47:197-208. Gill, CO. and Harrison, J.C.L. 1989. The storage life of chilled pork packaged under carbon dioxide. Meat Science 26:313-324. Hanlon, J.F. 1984. Handbook of packaging engineering. McGraw-Hill Co., Inc. New York. Ho, C.P., Huffman, D.L., Bradford, D.D., Egbert, W.R., Mike], W.B. and Jones, W.R. 1995. Storage stability of vacuum packaged frozen pork sausage containing soy protein concentrate, Carageenan or antioxidants. Journal of Food Science 70(2):257-261. Jeremiah, L.E. and Greer, G.G. 1982. Color and discoloration standards for retail beef and veal. Agricultural Canada Bulletin. Kraft, A.A. 1986. Meat microbiology. In: Muscle of Food. P.J. Betchel (ed.). Academic Press Inc., New York, p. 239. Lacroix, M. 1995. Antioxidant properties of natural substances in irradiated fresh poultry. FAO/IAEA. Lambden, A.E., Chadwick, D. and Gill, CO. 1985. Technical note: Oxygen permeability at sub- zero temperatures of plastic films used for vacuum packaging of meat. Journal of Food Technology 20:781-783. Lawrie, R.A. 1983. Meat Science 3rd Edition. Pergamon Press, USA. Lynch, N.M., Kastner, C.L., Caul, J.F. and Kroft, D.H. 1986. Flavor profiles of vacuum packaged and poly vinyl chloride packaged ground beef: a comparison of cooked flavor changes occurring during product display. Journal of Food Science 51:258-262, 267. 30 Maneesin, P. 1995. Product-package compatibility of sliced ham: Effects on product quality and film properties. Unpublished AIT thesis No. AE-95-10. Bangkok Thailand. Matulis, R.J., McKeith, F.K. and Brewer, M.S. 1994. Physical and sensory characteristics of commercially available frankfurters. Journal of Food Quality. 77:263-271. Molins, R.A., Manu-Tawiah, W., Amman, L.L., Sebranek, J.G. 1991. Extending the color stability and shelf life of fresh meat. Food Technology 45(5):94-102. Newton, K.G. And Rigg, W.J., 1979. Effect of vacuum packaging and film permeability on storage life of meat. Journal of Applied Bacteriology 47: 433-437. Noochpramul, K. And Loaharanu, P. 1974. Elimination of Salmonella from fermented pork by gamma irradiation. Office of Atomic Energy Office, Bangkok, Thailand. Pszczola, D.E. 1995. Packaging takes an active approach. Food Technology 49(8): 104. Rigg, W.J. 1979. Measurement of the permeability of chilled meat packaging film under conditions of high humidity. Journal of Food Technology 14:149-155. Rosset, R. 1982. Chilling, Freezing and Thawing. In: Meat Microbiology. M.H. Brown, ed. Applied Science Publishers, Ltd., London. Rousset, S. And Renerre, M. 1991. Effect of CO2 or vacuum packaging on normal and high pH meat shelf life. International Journal of Food Science and Technology 26:641-652. Seideman, S.C., Smith, G.C., Carpenter, Z.L., Dutsen, T.R., Dill, C.W. 1979. Modified gas atmosphere and changes in beef during storage. Journal of Food Science. 44.1036-1040. Thayer, D.W. Boyd, G. and Huhtanen, C.N. 1995. Effects of Ionizing radiation and anaerobic refrigerated storage on indigenous microflora, Salmonella, and Clostridium botulinum Types A and B in vacuum-canned mechanically deboned.chicken meat. Journal of Food Protection. 58(7):752-757. Young, L.L., Reviere, R.D. and Cole, A.B. 1988. Fresh red meat: a place to apply modified atmosphere. Food Technology 42(9):65-55, 68-69. TH9900006 31 TH9900006 fl iflicy lias Inino jj i nniii 10900 5795230 Tniim 5613013 2 nas 3 nTmrna m590f115lfl'tfV( 2 uas 3 nlainio 1-2 ims; 1-3 log cycles mjjaimj T^IEI^BIUQVI Lactobaciiius spp. fmmufifhJfinaj 2 nlam5w tnuiTtiiiiaitiivo Escherichia con tins Staphylococcus aureus ^So^ji^MJJfl wn«lliwuilo Salmonella spp. fin TBA number •UQJUOT'llJflmtlfJ^llJatTuJ^lWU^ t^ pH • y • J^'^HnTJ ai'Nfri30' 32 Effect of Gamma Radiation on Quality Changes of Fresh Ground Beef Saovapong Charoen and Kovit Nouchpramool Biological Science Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok 10900 Tel.5795230 Fax.5613013 ABSTRACT The effects of gamma irradiation at doses of 2 and 3 kGy on bacteriological, chemical and sensory quality of fresh ground beef were investigated and compared with non- irradiated controls. Changes in bacterial counts, pH, lipid oxidation (TBA number) and sensory o quality of those samples were determined on the next day after irradiation and storage at 3 C. The results indicated that irradiation at 2 and 3 kGy reduced total aerobic bacteria counts by 1-2 U3£ 1-3 log cycles, respectively. Lactobacillus spp. was also decreased significantly. Irradiation at 2 kGy eliminated Escherichia coli and Staphylococcus aureus. Salmonella spp. was not detected in both non-irradiated and irradiated samples. TBA number of irradiated fresh ground beef ball was significantly increased whereas pH values tended to be decreased. The sensory test showed that color and odour scores of fresh irradiated samples and colour, odour, flavour and texture of fried irradiated samples were not significantly changed from those of non-irradiated controls and were accepted by the panelists. Dosage at 2 kGy appeared to be sufficient for improvement of bacterial quality of fresh ground beef. 33 unvn usnnifii u m0 motJ fi.fr. 1993 V m E. con O157:H7 ( Mermelstein, 1993 ) 109 staphyiococcus aureus entrotoxin 2424) ( Clavero et al., 1981; Fu et al., 1995; Thayer et al. 1985 ) 1'U9njJil?s;mffn 103 ( vi.fr. 2529 ) aM iJvi In trnwn 3-8 y 34 y 2.1 h 500 s 300 nfu Gamma Cell 220 2 nat 3 nla 3 0 n 39 2.2 coliform, Escherichia coli, Lactobacillus spp.,Staphylococcus aureus ilftZ Salmonella spp.m5WT1fll*151/9^ Speck (1976) y i y fmiiun?9 Mesophiles yhlufjjfnUfjUgaiVtfmvi 37 ° 17 "^ Pseudomonas spp. VI'l'tatJmJfl'linijTflTflllDm'llJ P1A agar M^'OiniJJJ^ 90JMfjW 20 ""S 2.3 fniw^ifliinnsvfvn-JifiS •vhfmilfmSVnJnnflJ Thiobarbituric acid l«al^lB«U9^ Vyncke (1975) UftSlVlfh pH AOAC (1984) 2.4 10 nvi UQi' nan 4 uivi 9 -6 = 5 = 4-1 = ANOVA Larmond (1977) 35 0T''] i.3Oxio - 3.00x10 vifefifhmamYhmj i.i9xio7 ifiTauwenfu Psychrotropes fillfinfUWinrmUllflYHitJ Mesophiles ijJinu 1 log cycle 1-2 log cycles 6.6Oxio4- 2.ooxio6 Tfilauwentij wfeSfhmamvhnii 6.2ixio5 2-3 log cycles i.2Oxio - i.ioxio Iniafiwonfjj MfoSfiimamyiinu 2.5ixio iJlJJIQJ Lactobacillus spp. ims Pseudomonas spp. 'lumO'JQfrflllflijJQIof^ Sfil 3.50x10 ims; 8.i4xio4 Tfi1ayfi0nf3J?njjai«iiJ mimt/f-jtiJfjJiQi 2 uas 3 Lactobacillus spp. 3f(fl-3 3 U9S 4 log cycles Pseudomonas spp. fl^lfl^ 3 log cycles y 2 nlmfntmUJI^CIYhinmTta Escherichia coli UBS Staphylococcus aureus 1«M3J« 3 nlmniWtnwiTtiiiisnoi^O Coliforms, Escherichia coli , Staphylococcus aureus Pseudomonas spp. 1^MW« Wam7W5'3flW')0t)i-J11>3mtlimj;ljJ«l«?'^^fl1U'3l4 39 y ^ Salmonella spp. lJ^ 1 im^-JHUIIO-lf^SunjJin^fiwOflT TBA number lias pH y y f^ 2 llfis; 3 nTaiflSO >iilMfl1 TBA number VQAlUQIlftft'UftqM *H as pH TBA number uas pH U8>jm0T'itf«iJfiuwnw'i nnu • - ^ " 36 uB^ inii i.i9xio7 Ifilaueianni tf-iiflufl Tiwari ims Maxcy (1971) U.S. FDA (1984) imsi3T3iiuoff«fniS^aT4yi1tn»Jinu 2xio - 5xio iit (2524) 5 2.5xio5 - 2 nimnifj ffnui^onfifliUQVjiiijfi^i'fomMUPifi-jl^' 1-2 log cycles liasiliifntJlVO Staphylococcus aureus ims Escherichia coli iflMJJW iTiyi^S Salmonella spp. lU4miflllJWUTfaluni8«14fl1uf^Uas1wniwf^ mi«nt)^^it)il?jjiaj 2 nlainiw fniJi5Cia«il?uim Lactobatiiius spp. uas Pscudomonas spp. 1(30-5 3 log cycles l^fJIOilM Pscudomonas spp. v v 2 "tfCfifl i48nflinfls;3waw'0mim'ii^E)U8^m8JT?iuf8 fnn u^ ( Stuzt et al., 1991 UBS ^miau, 2537 ) fli TBA number malonaldehyde waiiiWUflBivm miflifjf-J^'MllKfil TBA number 5u 2 nas 3 V m0T'3 ( ivmiHAfi , 2539 ) imSJWawnQl'nmO^'w'lOU'n ( Luchsinger et al., 1996 ) •n^fiBiflmB-iflinB^jjaBfnf^snnmiRitJ^^iJfuiQJsf-jn-iiSiJinn'ii rhlwilgfmn V 8 a n ii eiru m a >31 m w vi fN 37 Sfh TBA number fY-1 1.6 - 2.5 SfianiJJ malonaldehyde snOfTUlflfjJ tfvi n-3imifii TBA number n 1.0 1!KJlll^4^lJ^H5JJVIU'i^m0^K-Jlll^4?S^lJ^H5JJVIU'i^m0'^'^«lllIw2naui^^' J ( Mattison, 1986 ) UW Sudarmadji Ufi^Urbain (1972) TIO-JIUQI ll?JJ1Qif^^ 2.5 • ( threshold ) ^w 3 mo 1-2 log cycles Escherichia coli Uf\Z Staphylococcus aureus Ifi i mapping lias; process control Wl?fJ'U 1. 9?tn "tfiniTUYlT (2524) 2. fnsmUfiflB'lifQiff'lJ (2529) iJlSJfnfffl^syin^tnBIIfUijUfllJlJ^ 103 (W.tf. 2529) 3. iJien i\)amfT5wT s (2524(2524) 4. i?n5tuj mqjfosflisfja (2537) }J H TJ Yl tn 3 tJflN II3 "114 fl?Um 5. ifmvufl isifcy uas Irmio ^uihzya (2539) 6. A.O.A.C. (1984) Official Methods of Analysis. 14th ed., The Association of Official Analytical Chemist, Virginia. U.S.A. 7. Clavero, M.C., et al. (1994) Appl. Enviro. Microbiol. Vol.60, p. 2069-2075. th 8. FDA (1984) Bacteriological Analysical Manual for Foods 6 ed., Food and Drug Administration. Bareau of Food Division of Microbiology, Washington D.C. . 9. Fu, A-H., et al. (1995) J. of Fd. Sci. Vol.60 No.5, p. 972-977. 10. Larmond, E. (1977) Laboratory Methods for Sensory Evaluation of Foods, Publication 1637. Canada Department of Agriculture, Canada. 11. Luchsinger, S.E., et al. (1996) J. of Fd. Sci. Vol. 61 No. 5, p.1000-1005. 12. Mattison, M.L., et.al. (1986) J.of Fd.Sci. Vol.51 No.2 , p. 284-287. 13. Mermelstein, N.H. (1993) Food Technology Vol.47 No.4, p. 90-91. 14. Speck, M.L. (1976) Compendium of Methods for the Microbiological Examination of Foods American Public Health Association, Inc., U.S.A. . 15. Stuzt, H.K., et al. (1991) J.of Fd.Sci. Vol.56 No.5 , p. 1147-1153. 16. Sudarmadji, S. and W.M. Urbain. (1972) J.of Fd.Sci. Vol.37 , p. 671-672. 17. Thayer, D.W., et al. (1986) J.of Fd.Sci. Vol.60 No.l , p. 63-67. 18. Tiwari, N.P. and R.B. Maxcy. (1971) J. of Fd. Sci. Vol. 36 , p.833-834. 19. Vyncke, W. (1975) Feete Scifcn Antrichm Vol. 77 No. 6, p. 239-240. 39 inmihio 1Ifjnuifrt! (nlmnio] 0 2 3 Mesophiles 1.30xl06-3.00xl07 6.60x104-2.00xl06 1.20xl03-1.10xl06 ( 1.19xlO7) ( 6.21xlO5 ) (2.51xlO5) Psychrophiles 7.40x106-4.90xl08 5.40x104-2.00xl06 5.40x103-3.50xl05 ( 1.29xl08) ( 6.55x105 ) ( 2.34x105 ) i Lactobacillus spp. 1.30xl04-1.40xl0? <10- 1.70xl04 <10 - 3.60x10 (3.50xl06) ( 3.83x10*) (7.21X101 ) 1 Pseudomonas spp. 5.80xl03-6.50xl05 10-2.50xl02 (8.14xlO4) (40) (<10) Coliforms 1.10xl04->2.4xl05 <0.3 - 0.9 <0.3 E. coli 7.0x102-4.6xl04 <0.3 <0.3 2 4 Staphyloccus aureus 3.0- l.lxlO <0.3 <0.3 Salmonella spp. Not Detected Not Detected Not Detected CFU/g 13 MPN/g 40 TBA number (wn. malonaldehyde/ nn.) I TBA number pH pH 44 ii Tiijjgiefn TBA number uas; pH TBA number nas pH ( P > 0.05 ) * iHuiw^JI (fHmnw) 0 2 3 t? mail) 6.73 6.82 6.89 7.25 7.22 7.29 nluj msflu 6.15 6.05 6.01 meqn 7.20 7.10 7.21 7.15 7.13 7.40 dl or a/ 4 7.19 7.11 7.19 10 10 ( P > 0.05 ) 41 TH9900007 TH9900007 15N mnun i mwua fninmfmirmm S\^WJ nnu. 10900 In?.5794114 USWiVU DTSEJl-SQI hi - nimn '5N isotope dilution technique - 15 im-jirnviilgnpnu lu'Hu^^Smi^iinaiiimsiijffunaii^inrim^^^S 15N mivififi0-3viu'inoimao-3(?if^1'ulpmiou 36.72% 1)0-31'ul^ilDul'U'Un M10 8.1 niflflfu N/l? Oll'HflOa (« 12% luilmnims; 27% lutlvmo-a "K^ 8, 16 ims 24 ninnfu N mM milfrijo ^jilo O^ITT 8 nlanfuiuiw^mj/l? nunu 14-29% 42 N-Fixation of Soybean and Residual Effect from N-Fixation of Soybean to Rice Yield in Rice-Soybean Cropping System Using N-15 Technique. Chitima Yathaputanon, Pornpimol Chaiwannakupt, Jariya Prasartsrisuparb and Thienchai Arayangul Nuclear Research in Agriculture Group, Agricultural Chemistry Division, Department of Agriculture, Chatuchak, Bangkok 10900. ABSTRACT A field experiment was conducted for long term rice-soybean cropping system at Chiangmai Field Crop Research Center, to estimate nitrogen fixation of soybean and residual benefit of the soybean stover to a following rice crop. Nitrogen fixation was extimated in the soybean using N dilution technique and non nodulated groundnut as a standard crop. To estimate the residual nitrogen benefit to the rice crop was calculated by nitrogen-15 yield of rice where the soybean stover was either removed or returned. In the first year soybean fixed 48.42% of their nitrogen which producing 50.31 KgN/ha. Residual effect of soybean stover returned was 36.72% of nitrogen in rice which equal 50.62 KgN/ha come from the soybean returned (stover plus root and nodule under the ground where the soybean stover was returned). The residual nitrogen-15 in the second year was too low to detect. No nitrogen fertilizer applied to the following rice plot where the soybean stover was returned, grain dry matter yield were up to 12% (Is year) and 27% (2" year) grater than in the plots where the soybean stover was removed. These benefits were comparable with applications of 50, 100 and 150 kgN/ha nitrogen in the form of urea. 50 kgN/ha urea applied to the following rice plot where the soybean stover was returned produce the highest grain dry matter yield which were higher 14-29% than the plots where the soybean stover was removed. 43 50 jf IJV (De et al.,1983; Nambiar et al., 1982; Giri and De,1979) lU0^infl1flfn?wl-3luTnilflU«in0imftW1TJinvn^^uyi1«1^ ^ ririlM Eaglesham et al. (1982) 1u nn u tnuiia 3J 60 flD.6 U1 90 1ul?11l1O'U-15 5% atom excess condenser UfJS spray trap mfilV stainless steel 15N International Fertilizer Development center 44 I5N/14N Kmio-NflioufliotJ-nfln LEYBOLD - HERAEUS CM 330 UflSlflf O-nfl Emission Spectrometer W11 JASCO N-150 S Texture tflu Sandy Loam pH=6 OM=0.63% P=112ppm K=72ppm S=20ppm CEC=5.18meg/100fl1W Sand=58% Silt=26% Clay=16% 2 ilnn tJas 2 qqma n V RCB S 4 «5i l iJgntnmMn -WIJ^I^O^IVIJJ 60 2 3 iJgniinlvifl mi^mulMii 90 4 ilfJoowr Split -Split plot in RCB U 4 Main plot: fl11UQ5Yl 1 2 3 4 Sub plot : iJuluinilflU 4 fminiiYi l Irfijw o nlaniN luimmj / \i 2ief^t) 8 nlanfii "hjlprnflu/ii 3 Imjtj 16 nltinfu liiiwmu / TJ 4 IH^w 24 nlnnfu IUIWIIBU /1? Sub - sub plot: a"" 1 2 45 N-15 8u. x ION. mJa^ieiiflviiJS'U'uiPi 2u. x 2u. 50 «K1J. lllui^ qgmavi l y t 20CKJJ. isvnuum 20 im. uasilaotrmjYn'uiiJm 45% P2O5 s«n 9.6 nn. p2o5 60% KjO O^TI 6.4 nn. Kp Well tTQVJ^IuT^ilflUiTTHflJUlJfl^wnwH^liY^tJJJlit) 46% N 3.2 nn.N noli imsiiiila^iol'Klviillif^fj 5% at. ex. N-15 jjilo 8?)7i 3.2 nn.N. 4 ffiw (sub plot) \j V 1 j^ pi'n^ffiu'osS^^ 4u. x 5u. 4 isiwu lJ \49nioinSluuplas!tfii4 (sub plot) uii-j'wvi^geniilu 2 muvnu (sub- V 1 sub plot) 1fimiila™?iwafl'os5miYi'U9-a 1 fTTudoo iviinii 2w. x SJJ. m nu IJJ. x 2JJ. 45% P2O5 19.2 nn. P2O5 m\i ims1iJiinm5tJiJfifi9li« ewn 9.6 nn.icp w v 46 % N D?)7i 0, 8,16, ims 24 nn. N woli Ifiunii-ilff 2 nf-3 n asiviinu f-j^ 2 amnmen'ne-a iIn«Tunl4f?sos 25 x 25 ^u. (total nitrogen) H2SO4 WU^lisnuiB Kjeldahl (acid digestion) ^oSinfjillflf) Bremner (1965) H2 so4 itfjj^^^fuMfjC 150 °c nm 2 "WIIJJ^ uasogamnuwigwiwwtaliJYi^'Hmi 350 iiluntn 2 •ffiIu-3 vh iJiuiifunwiuf^iniastntj^nnvii^i iJfufmui'uij^uuo^ N uaijjTifigwnjTTu 15N/MN Dumas (dry combustion) ^ofuitlllT^KJ Dumas (1834) ims Fieldler llflj; Porksck (1975) flit) Emission Spectrometer (Jusco Model N-150) i ^ 2536 - BtJQIflJJ 2538 46 2536 - BtmfllJ 2539 flntmsm (Hvi I n l iJvi l 8.05 (48.42% Ndfa) 5N-Dilution <9 A a V V fio 7.90 (47.46%Ndfa) *d \ tv «v w (tl^ n 36.72 iviinu 8.10 ffiuwfi^fini-3ioifimi3!'Dfifiiic!Bin<8'n1'VNfi 22.13, 19.29 nas 24.97 3.27, 2.43 ims 3.66 d*- <^ 15N mat I5 N 15N 5N 5N (A!Y\ 2) 5% at.ex. 3.2 nn 15N lumivififie^iJ^ 2 15N (lf\ '5N Emission Spectrometer ims Mass Spectrometer) 47 w il? 0.0701%N w&ifmilgn'fmiviiJYi 2 V (I) 0.083 I%N R SfiimntJiviinu O.O763%N i4iMTj ?m VIUQI •monaijTU r V i> i yi (vilJuivmuvn'NiiJai) «w uaslu) rninu 16.68, 8.91, 6.56 ims 8.69 284 minu 357 4.46 nlnnfuiviifiiisivifisli imsntyi 384 97 n1anfuma?i?i9li nai 430, 387 ims 957 mint) 3.18, 4.42 uns 8.63 oimaQ^ •ii•iifniviff i 2) mm wim (oimaa-3) fsytyw^ ims (I) (R) 48 I ivhfhj 20.4-22.9, 4.5-7.9, 1.6 - 1.9 lias 4.7-5.2 J R v < wawaw (iiTHiInmnw) •uo^rimaQ-jmnnii 292-348 iviinij 202-228 nianfu^ei? if^Silfinaiiwlwiifluminii 2.6-3.2 n ]fitJ'Hfl-3flnn'nmuintnHfiwas?itu9-3iiin1vifi 217-232 nlanfumaflploli 42-52 nlanijjiunfipiQii ufoi^mjfifiiJifminnvhf 296-404,23-28 ims 499-562 nlanfuwei? wSiJ?}jnQj1 ^Snamtinyi^iJqn1uqgiu?nuasogini](j N 2 ilvi l 8 ims 16 214 nlafnupieii (•onn 740 iilvi 954 nlnnfuwQii) ims: 147 («in 850 t3"u 997 nlnnfu^iaii) ^iwan^ij imsmalfr^tj 0 ims 24 nlanfu 91 nlnnfuwaii («in 760 nta 851 ieii) uns 77 nianfu^ial? («in 782 ii5vi 858 nlanfueiaii) wuj^i y » if irns 24 nlanijjlul?m!)i4?ia1i I«oSv3TniTniua«<(jnmjj i v SfHijfifl#nimjiJU no fUanfyfrn'ta1 Onn 605 nJu 715 nlanfupieii) nas 102 iuwoli («in 748 ILIVJ 850 nlanfueielf) enuaimj ujeSfmlffiju 8 uas 24 afi'i muiiw 125 nlanijjwoli («in 910 ifl%4 1035 nlanfuwoli) u?is 166 853 iilu 1020 nlnniuwoli) fliuth^u un^molrfijtj 0 ims; 16 api'unmjjnju 120 nlflniupieii (snn 688 iilu 808 nlanfuw'eli) uns 87 nlanfjjpioli (flin 775 i3u 862 nTaniuw'eli) «nwm 24 306 nlaniunoli (snn 710 tilvi 1016 nianfuwQl?) uas 0, 8, 16 lii w 754 - 854 lias 688 - 774 nlnnfJJWQI? 0, 8, 16 11ns 24 1 uinn^i^n'U0t)^SiTtidiflajvii-3tT^'8s;iiHi4ipi-iiiy0iij'5nnilal^tJtfiS wa gwijjoQma0^^2miui(i(inoinaiifli4giiiJa-3l'Mfii^a;piminij 851 nlanfu • y t wol? g 808 lias 754 niafiijj^oi? tnuansu 715 nlanfuwsl? SliJ 8 y 954 50 afl uasvlnffn vi5Hfiimin^yyiiJg]nltiqg]u?nuas8gmi|{j dlvin t V 2tlvi l ] 8, 16 s 24 nl?ini:')jllul«T5i9 ^ 2) 5 U 2 iJ^ 2 m?lifi]tJ89inni-3 n 0, 8, 16 ims; 24 (I-R) ii^npi^nuom^mijl^iw ^iw meltr^w9?in o nas 8 I-R ^iJgnwiuoimaB-jSfi'npf^tjfi (170 ims 89 nisfifupieii) menJiwumouniifii I-R viiJfjn 16 ims 24 nlaniJjl'u'taiiq'uwBi? fin I-R ^iJgn^nwoimliB^Sfinwifjw (82 uz\z 90 51 afl uasvlnffn enn-avi 6 th l uas:1ffi]{j0flneh-3 ^ ny liinu 2 Uvi 2 0, 8, 16 ufis 24 2) TJvi 2 u\ •ihi-cchiwae-a VIUTI 48.42% mmvhnii 8.05 vmri 36.72% 8.10 90 nianfii/iil'uiluin 170 8, 16 aas; 24 TumnJanim 214 nlamjj/b'Tutluin lias 89 n IJT3 - rQma nai 52 V Bremner, J.M. 1965. Total nitrogen, pp. 1149 - 1236. IN Method of Soil Analysis, Part II : Chemical and Microbiological Properties. Amer. Soc. Agron. 9 : 1149 - 1236. Dumas, J. 1834. Elemental analysis of organic substances. J. Pham. Chem. 20 : 129 - 156. De R., Yogeswara Y. and Ali W. 1983. Grain and fodder legumes as proceeding crops affecting the yield and Neconomy of rice. J.Agric.Sci.,Cambridge 101, 463-466. Eaglesham A. R. J., Ayanaba A., Ranga Rao V and Eskew D. L. 1982. Mineral N effect on cowpea and soybean crops in a Nigerian Soil. II, Amounts of N fixed and accrual to the soil. Plant and Soil 68, 183-192. Fieldler, R. and G. Proksch. 1975. The determination of nitrogen - 15 by emission and mass spectrometry in biochemical analysis. Anal. Chem. Acta. 78 : 1 - 62. Giri, G. and De R. 1979. Effect of proceeding grain legumes on dryland pearl millet in N.W. India.Exptl.Agric. 15, 169 - 172. Nambiar, P. C. T., Rao M. R., Reddy, M. S., Floyd, C, Dart, P. J. and Willey, R. W. 1982. Nitrogen fixation by groundnut {Arachis hypogaea) in intercropped and rotational systems. In BNF Technology for Tropical Agriculture, Eds. P II Graham and S C Harris, pp 647- 652. CIAT, Cali, Columbia. 1 ilfuifu N fmeif-a N2 mnginiff uas Pimm N (n.n.N/W) mieif ^ N2 WciflfWN'D'li jeigunviiJgm'nu wvq^vi 1 %Ndfa n.n.N/h" N ma?) + Y\ lu (n.n.N/1i) I R I-R n.n.N/b' thmao* 4.5 b 16.7 a 48.42 8.05 17.54 a 14.54 a 3.00* 36.72 8.10 3.3 b 8.9 b - - 16.07 a 13.36 a 2.71 ns 22.13 3.27 ffomnfljiflf3 N2 4.4 b 6.6 c - - 12.49 a 10.09 a 2.40 ns 19.29 2.43 vim 8.7 a 8.7 b - - 15.39 a 12.80 a 2.59 ns 24.97 3.66 % C.v. 38.6 26.7 - - (a) 26.9 - - (b) 17.0 if! a/ 95% %Ndfa = %Nitrogen derived from air I = incorporate R = Remove I - R = Hfipi'Nisffi'Nwawapi N CO 54 ) iffwinfvwiwimjnau (14.14. uaswawaei N 1) -3 (n.n./H) mum N (n.n.N/ii) d fa + ID fftl + llJ mafi + wu + ID 285.4 b 357.4 b 4.5 b 16.7 a 383.6 a 430.0 b 3.3 b 8.9 b 104.2 c 386.9 b 4.4 b 6.6 c w - 957.0 a 8.63 a 8.7 b % C.V. 33.0 30.5 38.6 26.7 95 % 55 3 mum (MM.mm) ifluinnvhmmjnaiJ (u.u.wuuasiTu) ims iiBUDQ^uaPi flu imslu) N2 m (ilvi 2) Mawnilvi l n"mvi l Irrijogiitj efanriu °) iwviTiinnje^qfjfna^ 2 •VYTjqftmfiYI 1 ihvmmm^ (n.n.Ai) (n.n.Ai) ftj+lu 111 i R I-R I I I R I-R N = 0 309 b 292 b 16.3 ns 202 a 3.20 a 20.4 b 20.2 ab 0.2 ns = 8 292 b 289 b 3.1ns 228 a 3.17a 20.8 ab 19.0 b 1.7 ns = 16 315 339 a -24.1 ns 216 a 2.72 a 21.7 ab 22.2 a -0.5 ns = 24 ab 302 b 45.5 •* 204 a 2.62 a 22.9 a 18.6 b 4.3** "Srnivifl 348 a N =0 207 a 9.8 ns 296 c 1.85 a 4.5 b 3.7 a 0.8 ns = 8 217 a 188 a 39.8 ** 330 be 2.12a 6.1 ab 3.1a 2.3 ns = 16 228 a 198 a 29.5* 373 ab 2.10a 6.7 ab 4.1a 2.6* = 24 228 a 208 a 23.4 ns 404 a 2.72 a 7.9 a 4.0 a 3.9** 232 a N =0 37 a 4.7 ns 23 a 0.25 a 1.6 a 1.1 a 0.4 ns = 8 42 a 51a 0.3 ns 26 a 0.27 a 1.9 a 1.4 a 0.1 ns = 16 52 a 37 a 13.2 ns 28 a 0.27 a 1.9 a 1.5 a 0.4 ns = 24 50 a 52 a -5.7 ns 26 a 0.22 a 1.9 a 1.9 a -0.0 ns V 46 a N =0 - - 531 a 4.70 a 4.7 a 3.8 a 1.0 ns = 8 - - - 562 a 5.20 a 5.2 a 2.6 a 2.6* = 16 - - - 499 a 4.70 a 4.7 a 3.5 a 1.3 ns = 24 • 500 a 5.10a 5.1a 3.1a 2.1 ns 95% I = In) R= v I - R = 56 l uaseVmijti N ii N/mqgvi l wawantfn (nn./b')ilYi l I R f^R I R S 850.8 a 759.8 a 91.0 ns 794.5 a 624.0 a 170.5** M 808.3 a 688.0 a 120.3 ns 764.0 a 671.3 a 92.8** G 715.8 a 605.5 a 110.3 ns 760.5 a 662.3 a 98.3** F 754.5 a 688.0 a 66.5 ns 792.8 a 655.5 a 137.3** j = 8 S 954.3 a 740.5 a 213.8** 753.3 a 663.8 a 89.5** M 1035.5 a 910.0 a 125.5* 794.0 a 745.8 a 48.2** G 893.0 a 725.8 a 167.3** 707.8 a 630.8 a 77.0** F 850.8 a 770.8 a 80.0 ns 730.8 a 657.3 a 73.5** = 16 S 997.0 a 849.8 a 147.3 * 762.8 a 680.8 a 82.0 ** M 862.3 a 774.8 a 87.5 ns 790.8 a 683.5 a 107.3 ** G 850.5 a 748.3 a 102.3 ns 836.8 a 687.3 a 149.5 ** F 854.5 a 774.5 a 80.0 ns 769.5 a 651.8 a 117.8** = 24 S 858.5 a 781.8 a 76.8 ns 736.5 a 646.3 a 90.3** M 1020.0 a 853.5 a 166.5* 833.0 a 720.5 a 112.5** G 870.0 a 737.0 a 133.0* 762.8 a 642.8 a 120.0** F 1016.3 a 710.5 a 305.8** 760.8 a 646.0 a 114.8** s = oimne-3 M = F = •mniTui'iJfh I = tnjrmuinfvmf R = I-R = uQGft,M,uuioin = >i •* 8I9T •«39fr> E£S8'£l «£l£-8I * 81S'£ «806>I «SJf8I O • * S9fS B£6I"Sl «8S£03 •* Z.06S B 09691 B 89833 JM su 595-3 EgSfZ.! B £3Z."6I S PZ = fr B£66£I Be£S'8l suoiS'Z B £^>l «£8691 J i o §09'£ B8H--9l B£S0'03 ** 0££> BS8£'SI «SU"6l S 91 = QJtL£WQ B099"3I ^ 8£SST su 8WI B88£"5I E S£67.I J BOWII «0£Z."W • SSre «S36TI B08T9l O B080>I ^05^81 * SOZ.'£ B SOS'SI B0I3"6I JM 'Z B0£0"9I ee66'8t su £6£T «8IS"9I 8 0I6"8l S 8 = • * S6I'fr B00/.£I BS68Z.I su^s-2 B 00871 B88£'5l d I *u L6?Z B S600I B£6^I O B8l8£I e00S"8I • 000'£ Z W[l (£|yN"UU) N WgMBM I U^t^/N'UU) N WBMUM I U&bftW/ ^u N fi[jL£WQsaii t uS Z,9 TH9900008 58 TH9900008 V V A.niger uasonwum mjfiini nnui 10900 5795230 fie 552 5620118 meJi uv fl0 15 U1Y1 llQlJi^^WI (control) 95 97 isolates fl9 isolate 2-19 "K 2 mi Increased Citric Acid Production of A.niger by Ultraviolet Irradiation Orawan Suksudej and Chanin Phangarakrachadet Biological Scinece Division, Office of Atomic Energy tor Peace, Chatuchak, Bongkok 10900 ABSTRACT These studied aimed to select the optimum time of UV-irradiation for mutation of A.niger . Citric acid producing ability of isolates were tested in order to screen mutant. It was found that the survival less than rl % was obtained from UV-irradiation for 15 mins. From the screening of citric acid producing ability, 97 isolates were shown the percentage of citric acid significantly higher than control at 5 % level. The highest amount of citric acid from isolate coded 2-19 was 2 time higher than control. 59 UYIWI (mutation) genotype tYiimcivi0m)ijmiiiJamjuiJf^in#1ms:mjTijmq?i uasiilmf mivm-avavii hv flsenn Hiroi nas fl«US(1979) Monascus anka pigment mumu 4-7 ivii Aspergillus niger 70 s; 12 18 Aspergillus niger u 1. fniumj 470 2. i 2.1 m?Qlfins;'HVn-3(5a\4Vi1ol^lllfi Plate, Micropipette imsTip, Loop, giJUtfg (Incubator), Iflfg^uulfllau, Haemacytometer, Hot Plate, Laminar Air Flow, Autoclave, Microwave, pH meter 60 2.2 fnnmnsjviyn^ifiD miin 3. OivnilfitHWO l#Ufi Potato dextrose agar 4. fliimS l&iri Iwauijlafliofl W(NaOH), demvta (KH2PO4),lL0JjlumWJjluifl?Vl (NH4NO3),Phenoptalene 5. O^mfUYil'iH'UfmibsimflWa I&lfi Lflfo^illlfliflOJJ'H'JlflOI.Ilbufnim-Ui^ll Window UBS SAS l. SmnrjtnYiminsfljjlufmfnuftfl uv U1W0 A.niger VM PDA slant Vimvil spore suspension I«Ul?fJ spore 110-3 A.niger 1JU PDA slant fl-alu 0.05 % tween 80 ll^lJiilJfliO^^tJWinmiJn^^'dni^Oll^ Via-J^nfi^lJitTQlJ^fiiB-J 1^rill 0,3,6,9,12,15,18,21,24,27,30 uifl UIIIJTJJJ^ 30° c iilunai 2 TU A.niger WVimnmViiWUTi \if)imi'\ 1 (fllUlluO-3 Alexander HflS Detroy, 1980) 2. ihlifO A.niger MM PDA slant JJIl^itiU spore suspensionlfltJliJtJ spore 1)04 A.niger MM PDA slant a^lu 0.05 % tween 80 U#llh1llniO-3#™H11)"nU"Uvi fl^^4^^4 spore \ PDA slant 3. 3.1 spore suspension lflm?tJ spore 0.05 % tween 80 \i\ih\llM spore Iflf/Hf haemacytometer Itfi^ lO'spore/ml.llllJflJJI 10 ml. lHjJ1fl5 50 ml. "hi flask Uinfl 250 ml. lUthvi 170 rpm lllvintn 7 TOI 3.2 v v < 5 ml Imulu flask uinf) 50 ml.iwjj^inaviis ml. phenoptaiine 2-3 Myfi ui!iJ1?ii?iivinii NaOH o.i N v t if v U (mutant) Otii-3SiJtJ^1flqJYn-3?rQ^1S;^lJfmJJlff]3J\jf0fJf1ff]3J\ S 95 UV IOT A.niger ^UfYfuivi Table ^ 1 VdJ-31 ne 15 ui^ mowinvinin'l'UfmQ'itjf^ uv 15 i 10tJ£1£ 1 Alexander Ht\t Detroy (1980) Table 1 A. niger counts at various time of irradiated Irradiated time (min) Number of colony** 0 ; 10x10* 3 33xl05 i 6 5 I 30xl0 | 9 23xl05 12 12xl05 15* 1 93x104 18 1 74x104 21 53xl04 24 47xlO4 27 31xlO4 30 18xlO4 ** Mean values from two experimental • of A.niger less than 1% Time that survival 62 2. V 13 ^0 ITHffliuivi 242 isolate A-x (nu 24 n^u) Table 2 D fl0 isolate 2-19 Table 2 The lowest and highest amount of citric acid produced from UV treated A.niger compared with control in different experimental group Group % citric acid Control Lowest prodproducini g ability isolate Highest producing ability isolate A 153b 1.05c 2.09' B 0.41' 0.34' 1.441 C 1.02' 0.50' 1.37" D 1.32' 0.74' 3.33'" E 0.83' 0.54c 1.19' F 1.16' 0.64c 1.83* G 1.05' 0.44" 2.04* H 1.46* 0.41' 1.97" I 0.74" 0.63' 2.24" J 1.50' 0.82' 2.08* K 1.57' 0.43' 1.81" 1 L 1.27' 0.71' 2.11 M 1.52' 0.62° 1.87* N 1.42' 0.76' 2.42* O 1.34' 0.40' 1.50* P 1.27' 0.37' 2.04* Q 0.96' 0.39' 1.51" R 1.17' 0.41' 1.49a S 1.20' 0.78' 2.03* T 1.16' 0.52' 1.65' U 0.98' 0.62' 1.08" 1.50" V 1.07' 0.59' 2.07* W 1.57' 0.90' 2.33' X 1.03' 0.36' Means followed by the same exponent letter in one group are not significantly different at the 5% level Highest producing ability isolate is D 2-19 63 l. A. niger mi nu 15 M1Y\ i V 2. fmmmbsmi5fi"mm) A. niger 242 isolates 3. (control) 95 97 isolates uatisoiate 2-19 2m'n 2534. . 2526. ^ f, ^m'Mi. 288vi. Alexander, N.J. and R.W. Detroy. 1980. Mitochondrial mutation for clcohol production. Biotechnol. Lett. 5:165-168. Hiroi, T., T. Shima and N. Ogasanara. 1979. Hyperpigment-productive mutant of Monascus anka for solid culture. Agr. Biol. Chem. 43(9):1975-1976 64 &°© (Plutella xylostella L.) j nviui 10900 5795230 W8 571 16-47 VuasfniJJihjmj'miis' 22-96 %) VIUQI 4 3.21±0.30, 5.57±0.60, 3.16±1.07, 3.43±0.97, 3.88±1.59, 17.72±2.74 ttftZ 16.16±3.93 lli W1JJ 13-31 QU ^tSoifun-jliJmQsiyifi' l iwims 17-248 vlo-jmao 109±77.60 vlo-a 4iimqvvvf)Af)$u (TC) < = 23.45 5t4 0Pi5imi uoit)'wi4^tjvi5 (Ro) = 25 unsoRSimimu^iiinDi^ (k)= 1.15 mat) 3.33 fif-a 55.89 % 0wnm?9nog-3tjPi'wiiluis:t)SHU0i4Tioiuns;2 (64.37%) im (49.64 ims 46.38 %) Ill llll llIM II™ U™ " TH9900009 65 TH9900009 Studies on Biology and Ecology of the Diamondback Moth (Plutella xylostella L.) Wanitch Limohpasmanee, Pravait Kaewchoung, and Ajaya Malakrong Biological Science Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok 10900 Tel 5795230 Ext. 571 ABSTRACT The diamondback moths, Plutella xylostella L. were reared with cabbage leaves under field condition at Khao Khor Highland Agricultural Research Station (16-47 °C, 22-96 % R.H.). st nd re! th The average duration of the egg, larval (1 and 2 instar, 3 instarand4 instar), pupal and male and female adult stages were 3.21±0.30, 5.57±O.60,3.16±1.07, 3.43+0.97, 3.88±1.59, 17.72±2.74 and 16.16±3.93 days respectively. Female laid eggs at 1 day old and the highest number of eggs nd were counted in the 2 day of the oviposition period. The number of eggs laid per female averaged 109+77.60 eggs, ranging from 17 to 248 eggs. The life cycle from egg to adult stage was 13-31 days. The population parameters were the cohort generation time (Tc)= 23.45 days, the net reproductive rate (Ro)= 25 and the finite rate of increase (A)=1.15 time per day respectively. Studies on reproductive system of this insect showed that the developed testes were th found in the 4 instar larva while developed ovaries were found after emergence. Male mated many times (average 3.33 times) while almost female mated only once (92 %). The ecological life table of this insect was studied in the cabbage field at the Khao Khor Highland Agricultural Research Station . The eggs hatch was 55.89 % and the highest mortality st nd occurred in the 1 and 2 instar larval period (64.37%). The disease and parasites caused the high mortality in the 4 larval and pupal period (49.64 and 46.38 %) 66 unui (The diamondback moth, Plutella xylostella L.) (cosmopolitan species) (F-i sterili l. 2. 3. 4. 5. y 6. ^ilnifuKiau^nurn wiu vjnu ijinnu ma fniasamfniluiaifliw 5 % 7. l.i. il 5 % nas 1.2. 67 1.3. 20x15x10 °»u. 1.4. 1.5. 10 °»u. ^ 15 30 na'o-a 2. 2.1. 2.2. 1-2 TIVI 2.3. 10 2 ^T m 3 10 ndo-j corpus bursae lias spermathecal gland Yjfnu 2.4. •un(nii^3j'3fj^m-399njJimti-3iwna10-3vimtTiniDvnf)i^'uwiffuyntn-3 loifij.m 10 10 «i ^'0030-3 spermatophore 3,6,9,12 imsi5 io V wi vh 3 ^i 3. 3.2. vn 3.3. ismmfl'uo-jfmmBuo^flnu^ 3.4. 68 l. l) v n-amvmi (Oval) fieuu"Nuuu o.29±o.O2 JJU. tJT3 o.5O±o.O2 uu. 3- 4 TU maw 3.2i±o.3O IU snQmfj\) id 1 JJ1ll^^-3^lJlJM^40^JNmevn m (Eruciform) 3 fj v\muu 5 n 3,4, 5, 6 uasiJ^e-Jtjwinio vmmjfi 4iu 5fji-2 Knm 5-7 5.57±o.60 3uns; 4 qs 2 vi 10 2- 3.16+1.07 iiuuas; 2-5 iv) mat) 3.43±o.97 IU 1 1-2 Q^ mat) i.ll±0.33 iw Obtect in jfl UinfU?il1U AflUfi 1-9 QVI mat) 3.88±1.59 TU nU1StJS;nai^ll9!i1lU9'UO9nil!vi^l'3l^JJT't) 13-31 QV1 V V .V mj'Haa 3 9U f (diamond mark) mo 69 100 80 60 40 20-I 40 30 4 20 3 10 «J* 0 J\ 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 I 2540 r ( vun u wv ymfi-mv v d v v *S I 4-21 114 mat) 17.72±2.74 TU uas 2-19 in iflfiu 16.16±3.93 iii QniiffnjmffwflemmiJtj mini) 0.85/1 isusriovn-nlii o-i 109.27+77.60 TVI 70 m^li)iajWljI?mas;fnia{ii9flD0-31HU91jlfJWfl, Plutella xylostella L. «TOW(ffj) fiiTEl (fa) riiM>8a(fa) wmime. % 1-2 449 5-7 5.57±0.60 35.63 IV 3 187 2-6 3.16+1.07 94.41 10 4 114 2-5 3.43+0.97 50.88 Will* 201 1-9 3.88±1.59 54.69 «/ d a< WIN 54 4-21 17.72±2.74 tfimti 47 2-19 16.16±3.93 0.85/1 flTUlVliii/PhuJEJ 1 f\l 30 17-248 109±77.60 V (innate capacity of increase) : rc= 0.14 ^QinipioT'u un (finite rate of increase) : X = 1.15 ehpisTV! WllStiliUli^liimaoi^i^i 1 2 M^flineeniiluwiilljJTioimsiliJjioiiiiflsa^ii-Jif00^ (iiJ'M 2) 140 ^ 120 -| 100 -^ 80 1 *5 60 3 40 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 (Plutella xylostella L.) 71 «n?ninfl (Piutella xylostella L.) (Ro) l OiqenmEJ (114) oVrcifmutnoww^ X K 19 0.0523 - - 20 0.0523 68.1891 3.5663 21 0.0491 72.5187 3.5607 22 0.0476 133.6725 6.3628 23 0.0439 55.7420 2.4471 24 0.0423 70.8951 3.1123 25 0.0423 44.3771 1.8772 26 0.0423 19.4826 0.8241 27 0.0415 9.7413 0.4043 28 0.0407 4.8707 0.1982 29 0.0362 12.4472 0.4506 30 0.0346 13.5296 0.4681 31 0.0306 8.1178 0.2484 32 0.0306 13.5296 0.4140 33 0.0301 11.3649 0.3421 34 0.0214 16.2355 0.3474 35 0.0214 9.2001 0.1969 36 0.0170 10.2825 0.1748 (Ro) = X LXMX = 25 mi (Tc) = Z (LxMxx)/X LxMx = 23.45 TU (rc) = ioge (R0/Tt) = 0.14 nmimiu fTYl f (k) = e*= 1.15 W-JWSTU 2. 10 72 flino (iiJvi 3A) ifmsnQun'Uiilumjifitnfhj iilinmw mwmwao-a j gyluti'affai'vis (scrotum) i 2 mifl rm eupyrene ibifiatmvmwmjniil'l VUeupyrene ims apyrene fl^nd'ltj'UJinij'lun^niJtTllJoiiJ (spermatheca) iSfJ ffiaJlJFnt) seminal vesicle ductus ejaculatorius duplex lllvivio^|lli"l'3lllli^'Q U fb'U'lJ'UflSJJ accessory gland lfj seminal fluid (fnii^'*iTH141^^tj1\4m?ditJV10PlttnJoilJ) weflifi ductus ejaculatorius duplex viodntlPfllloiU'OSJnjjn'Ulll'Uviot^fJT liofTJI ductus ejaculatorius simplex accessory gland ITllloiUimstTI'l-a spermatophore) llounu aedeagus aedeagus flsSWlVJ^^SUtJntJmilJwQniJ ductus bursae U0-3SnilStJ lit)fill vesica (endophallus) (¥-3^1T'314lJintlflsSanWfUS;ililjqumnffll4nufniWflW«n'lJ ductus bursae lioflli cornili l\4«ii?iJJTit)mff^ 0Qtns;^i)>N\j^ vesica ^i valvulae ^sojiluiJ^iQ^'no^iJ^iQ^^ 9 ims 10 ^uuoonui (11J ^ 4) S)j;S'K0-3^nTi!'lJ'n^li\Jims;W?t3J'W'U^U(jnnU (ditrysian) ipltlVQ^lllfl^i'HIU'il^iiilitinii ostium oviducts life ovipore cB-3SuU00'Ullnf13JJ lope Yulufm papillae anales UtiS papillae anales S)i:SnPin3Jm0Uf)^?inilUW'UU^^DtJltJU1iOintT'3t!'M0^llpi0-3^ 8 (apophyses anteriores) litJfm apodemes muluS 2 lM (ovaries) (ovarioles) V1U oviductus laterallis njJfl'Ulll'U oviductus communis (common oviduct) 91 vagina (fhuviinJWmj'WU^mJfmJailJ) ims ovipore ^O^WftW'W'U^litJnii ostium bursae 9s vi9ihspermatophore (liuflli ductus bursae ) 1ll?i9fTLI corpus bursae (vilflll spermatophore) im ductus bursae 10S;SttQu5u99nllJ?i9nU oviduct (111V1^1Yiditl1YllJ011J) liOflli ductus seminalis 73 VN oviduct 2 spermatheca (vhvi'U'lYUflimilloilJ) fl?)0$j sS accessory gland vesticulum vagina 1- 2 tnvi 45-60 0-8 mt mmm 3.33 fif-3 (92%) A. •cccmn' itind - VMWICTCDCC - ductw ^Kulaloriui duplex prin»r> rimpk, '•, duplitipna #e of frenum formarion ortkulv dmplcx ~ v«dca(enduphallui} Hdragui melluiordi xylostella L.) spermatheca accessory gland apophyses posteriorcs mathecal gland anus vulva ostulm bursae ductu!' duc.us bursac scmlnatls bulla stminalis (Plutella xylostella L.) 74 xylosteila L.) y t tfiYl 1 •rm2 «WTM 3 l 4 l 3 2 3 4 1 3 4 3 1 4 7 2 2 5 1 0 6 6 5 2 5 7 2 1 0 8 3 8 4 9 4 4 3 10 7 0 4 4.6 2.5 2.9 1-7 0-8 0-6 chmWDB^ spermatophore 1 > 1 3 30 28 2 6 30 27 3 9 30 27 3 12 30 28 2 15 30 28 2 150 138 12 27.6 2.4 3. 64.37% iriinu 44.09, 5.64,49.64 uas 46.38 % wiuaiwu 4.ims;«niifl 75 fia Trichogrammotoidea bactrae Nagaraga UV\Z Cotesia plutellae Kurdjamove J^ 5 16-47 22-96 %) {fooufmniei % fmniEJ X Lx DxF Dx lOOqx lii 728 r 321 44.09 1H\40t4T't) 1-2 407 fniumt f" 262 64.37 ati ^ ?sf)SD0-3ima^ ilfl^tifniwiE) •OTUTUYWIEJ % rmwiu X Lx DxF Dx 100 qx vfueino 3 145 fmww 1 0.69 4 2.76 3 2.19 5.64 MU0Vl5tJ4 137 51 37.23 17 12.41 49.64 69 14 20.29 uwumuu 18 26.09 46.38 37 (0^11fflV!(niW/(?llSf)) = 17:20 76 800 700 • I 600 • -£» 500 • IS r» 400 300 • 200 • 100 0 MWOWTU3 , vm0\4iiti 1-2, vmouiu 3, mitmiviv 44, sniiflinmvmw minii 3.21+0.30, 5.57+0.60, 3.16+1.07, 3.43+0.97, 3.88+1.59, 17.72+2.74, 16.16+3.93 TuenucnaiJ nuisusnai 13-31 IIJ (nnScjiijjQi-ainii^on^j 1 2 TU ^iSwi^liiifli n-248 may 109+77.60 rlo-a w (2520) fim;jjiwfi(2526) Ooi and Relderman(1977) ims Hill(1975) tvu iilu fi •w'weivni Hill (1975) 3-8 lU 1s;fJS;M'U0'ul6t(nan 14-28 IV, I 5-10 TIIJ Ooi and Relderman 1 Ulio/ a/a* (1977) viimistjs; ID 3 QTJ istisnviovi 4 IU 6 TU fi 3.7 QIJ enm ID I^IO-J 248 l lltnj(2520) imSQi7?3V 3-4 iu i^ossniiluio 5-7 37-407 sfjsviWQ'u 6.2 QTJ flmiHQfifinu 3 fif-a flnupi 3.3 iu 1 1?mn(2528) vniiiMuowlownSisoslii 1-2 TU ISEJ^VIUQU 6- 17 114 IZUzmm 2-4 5l4 liasiSJOSin'JlWUlfJ ll-20 l\l 'iZUIi'nmif)VlUT)M 1 lU Singh and V Singh (1982) :iej-3TU'ii9ivni3wfi^0is;fJs;nfn^m^s)?aji^ii]piD9-3'H'U0'u1tJwn iiu onafj-3 l^i 16.9 iu onmo-j^QwiTiwnmpi Knm 18.1 18.9-19.5 lu 23.45 1M cB^fJm\4Hl4n'il1im>N (2528) l 25 ivii im 77 inn winvnaunfnvitn wimwu8u1uwnijoemm?fln T'fJ 4 ufo«Ul«WinuluMU0'UHK?0rn'u'lMt|j (Holt and North, 1970) (Lai-Fook, 1982) i: (scrotum) luisuswQiwj spermtogonia lias spermatocyte tf chromosome 3.33 (92 %) I'tfUl^tJ'JnU'Ue-J Cercyonis pegala Fabr. (Burns,1968) ^'llSfJlOS;1fll1'lJ'M-3 seminal fluid, eupyrene UflSapyrene sperm O' spermatheca 200 l mimj lio 64.37 % iv 3 Smo-jmnuotj noili^uiai 5.64 % ehvm'uo'untj 4 uas^nuw 78 ffeitasintu 37.23 ims 20.29 % imsSmiflimijawnmiyhmEjnjfHiifluiiJtJvi ivhnu 12.41 nas; 26.09 % Trichogrammotoidea bactrae Nagaraga, Cotesia plutellae Kurdjamove UASenHIPnenHIPn ^ ITfU H9\ U A . 2526.205 u. . 6. 2516. 523-542. ). w.ifi««im?T?)i, n^mni. 2528.85 u. imu v). u.inuflifntrwf, n^mni. 2520.90 u. Bums, J.M. Mating frequency in natural populations of skippers and butterflies determined by spermatophore counts. Proc. Nat. Acad. Sci. 61. 1968. 852-859. Coss, H.M. and D.G. Harcourt. Photoperiodism and fecundity in Plutella maculipennis. Nature. 210. 1966.217-218. Harcourt, D.G. The development and use of life table in the study of natural insect population. Ann. Rev. Enmol. 14. 1968. 175-196. Hill, D.S. Agricultural insect pest of the tropics and their control. Cambridge Univ. Press, London. 1975. 500 p. 'olt, G.G. and D.T. North. Effects of gamma radiation on the mechanisms of sperm transfer in Trichoplusia ni. J. Insect Physiol. 16. 1970. 2211-2222. i-Fook, J. Testicular development and spermatogenesis in Calpodes ethlius Stoll (Hesperiidae, Lepidoptera). Can. J. Zool. 60.1982.1161-1171. , P.A.C. and W. Relderman. A parasite of the diamondback moth in Cameral Highlands, Malaysia. Malaysian Agr. J. 52. 1977. 77-84. S hoy O. , P. Keinmeesuke, N. Sinchaisri and F. Nakasuji. Development and reproductive rate 79 of diamondback moth, Plutella xylostella from Thailand. Appl. Ent. Zool. 24(2). 1988. 202-208. Singh, S.P. and D. Singh. Influence of cruciferous host plants on the survival and development of Plutella xylostella L. Rev. Appl. Entomol. Ser. A. 71. 1982. 154. Sivapragasam A., Y. Ito and T. Saito. Distribution patterns of the diamondback moth, Plutella xylostella (L.) (Lepidoptera: Yponomeutidae) and its larval parasitiod on cabbage. Appl. Ent. Zool. 21. 1986.546-552. Stepanova, L. A. An experiment in the ecological analysis of the conditions for the development of pests of cruciferous vegetable crop in nature. Rev. Appl. Entomol. Ser. A. 53. 1962. 172. 80 mfi 4 0* fl V 3 nviui 10900 Ivti. 5795230 WB 551 ln??n? 5613013 nsuiyitnfnttwffnsimvio t\\i\im~\\i\i'n 11000 Ini. 5899850-8 fitussint/w? u'HiQYioiamnwMifnnni nnui 10900 .5791026 57 lei^mvi nun 3 imd-a 58 15 if v Erwinia carotovora subsp. atroceptica 18 f l tu 17 JJU. uividflfl^iimntlllitfo Bacillus spp Pseudomonas vesicularis TH9900010 TH9900010 81 The Cultivation of Antagonistic Bacteria in Irradiated Sludge for Biological Control of Soft Rot Erwinias : Screening of Antagonistic Bacteria for Biological Control of Soft Rot Erwinias Ngamnit Sermkiattipong , Leelaowadee Sangsuk , Penkhare Rattanapiriyakul , 2 3 Surang Dejsirilert and Niphone Thaveechai 1/ Biological Science Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok 10900. Tel. 5795230 Ext. 551 Fax. 5613013 2/Division of Clinical Pathology, Department of Medical Sciences, Nonthaburi. Tel. 5899850-8 3/Department of Plant Pathology, Faculty of Agriculture, Kasetsart University, Phaholyotin Rd., Chatuchak, Bangkok 10900. Tel. 5791026 Abstract Pure cultures of 57 bacterial isolates for antagonistic activity screening were isolated from three areas of soft rot infested vegetable soil and 58 isolates were obtained from commercial seed compost and seed compost product of Division of Soil and Water Conservation, Department of Land Development. A total of 115 bacterial isolates were evaluated for antagonizing activity against Envinia carotovora subsp. atroceptica in vitro. Out of them, 18 isolates were antagonists by showing zone of inhibition ranging from 1 to 17 mm by diameter. Most of antagonistic bacteria were identified as Bacillus spp. whereas only one isolate was Pseudomonas vesicularis. 82 1. 1111141 mi 3 2. 3. (2) 50% (trace elements) IU41 mfaw vuitJ ifan snrru ( Bacterial soft rots) inflflinn?0UUflYu1tJ f finu-j munufntn ims; uennn USL?0 <6> wow Hfinifl yifn mm nw^lu iai 1I0 Erwinia carotovora 83 wuo <7) 9f MM trvwiuufivuioviffHifon i (carrier) non (sludge) «1tJ5-3milutn?vnMS; (carrier) 2. 2.1 S«€QV1ti1fntTnni Erwinia carotovora subsp. atroceptica (Eca) «tf-3 2.2 mtneifraufni»4fn}4i^ci1\4fni'»iiliHin«iTifiii94i«a soft rot erwinias <7) uas; Schaad (8) latimo-Jlfe Eca HmtyUUOTHI? nutrient agar (NA) 24 Vliu-J fliniTliUIWeililwioJJllIu bacterial suspension liTSfil optical density (O.D.) ibsUiflJ 0.2 YlfnilJOnflflUUfr-J 590 V bacterial suspension f«iJintj^ wililijjj^^fUMfjS'HB-jiilunfli 3-4 in 84 2.3 fminuniotru fo s; 3 imftaffe ftflw st. (iovl-60) 2.4 mimi£JJJ seed layer agar i « Eca llJ0Tmim?n nutrient broth (NB) fiSlJf 1J1PI5 30 Ufi. IJlJ^^tUMfjfl 30°"B 18-24 UJJ. pmm) Eca fliw-jw i ua.wjnjlTimnijflnijeirni NA hum 9 ua. vortex mixer (o,m'HnS 2.5 W0 25 nfjjltYil4V4inril414^(Wni^OlJ?Un9T5 225 US. 1:10 2, 1:10 3, 1:10 \ 1:10 5 \.\f\Z 1:10 * fliuaimj I'WllllJflWgpl 0.1 Ufl. if V I I l:102 ltT{1-3Ul4SnumiJ;mtJ-3l*9^S seed layer agar ^^nfimiTly^© 2.4 tin 2 «ih (duplicate) 30°«« iilunai 3 iu fls (clear zone) lii (Eca) (Eca) Ul4O~m"ma{nm)'ltmi5 Disc diffusion method (9) luoivn^intn NB ^^fliMnw 30°^ iilunm 18-24 Spectrophotometer ^fniUUT3flflliim-5 590 UnluiU^I llflJfniU<\i'U 2.7 18 fifxmtnin'nmfimjn niuinaifnfffllfniimviij' Bergey ' s Manual of Systematic Bacteriology Manual of Clinical Microbiology 3. RntJii€! 3.1 Soft rot erwinias Soft rot erwinias (Eca) •yin 6 rnevi iJnngii nas;nsvi^iiJmnfioifnimims;0m-3mu1?i'^ ini^e Eca 3.2 v0iJgi 57 115 y y (Eca) (Eca) 57 5mm 2 (Clear zone) 4.9-5.4 JJ3J. 58 16 l.o-n.o uu. 86 115 "elinan wini 18 s (Eca) g Table 1 3.4 ii nms (Eca)< ut-3vi^Nn^'iJnng1i4 Table 2 Bacillus sphaericus llfit Pseudomonas vesicularis H3Jni5'fl'0nkmn B. polymyxa, B. sphaericus Has B. circulans 4. 115 lul^mvi gqis; (Eca) i y y 18 lT 3^^il^?]^ Eca flnnmiRUftruonflniSj'itnuni iJijflviiia^iiani^flinfJaMjjn 204 Fusarium oxysporum f.sp.cucumerinum, Pythium ultimum, Verticillium dahliae \>\,V\ZRhizoctonia , . (12) solani Table i qsnfoi&fam wfoomi 98 mflfPYnnu n.o JJU. ebun?01110? 43 lias 58 1.0 JJJJ. ihfnpifismyi 1^011101 98 U'ISIIIOII^L^O Eca l^«^q« ^ V V f Eca ta Eca •0114114 18 ^ Bacillus spp. uasSmmlolifmVllWtJl^llluif 0 Pseudomonas vesicularis a03fTlintJ^1V!n)03 Ferreira ef a/. ^fiaiTJI Bacillus spp. "K^nuo^ 5. subtilis S ?9 AUflioYtafnM^Iifim'y' 'M^Um0^U1 5. 1. Wiley, B.B., and S. C. Westerberg. Appl. Microbiol., 18(6), 1969 : 994-1001. 2. Sermkiattipong, Ng., H. Ito, and S. Hashimoto. JAERI-M 90-145, 1990. 3. Krishnamurthy, K. Sewage sludge treatment with radiation. National Seminar on Radiation Disinfection of Sewage Sludge for Safe Disposal. Office of Atomic Energy for Peace, Bangkok, Thailand. November 13, 1990. 4. Swinwood, J. F. The Canadian Commercial Demonstration Sludge Irradiator Project. The Joint IAEA CRP-ASCE TCRETWW Meeting. Washington, D.C., July 10, 1990. m. 21-23 m)ff?fntm 2537. 6. Ivilifly fowmif. waVninlifi'vn. wuwfn-jvi 2, fnimaw «nn«, n^iirwi. 2525. 1 y 1 7. ilinjiyi flumffi. m?iiJaw f 2532. 8. Schaad, N.W. Laboratory guide for identification of plant pathogenic bacteria. Bacteriology committee of American Phytopathological Society, St. Paul. Minnesota. 1980. 9. of^nvn nrnmuiwyftj fnifnol (Pseudomonas solanacearum E.F. Smith). n^tYTWI : QV101W Table 1 Suppressive test to soft rot erwinias (Eca) in vitro of antagonistic bacteria from natural soil and seed composts Isolate No. Diameter of colony (mm) Diameter of clear zone (mm) Clear zone (mm) 10 9.8 15.2 5.4 43 9.7 10.7 1.0 51 10.1 11.7 1.6 58 7.6 8.6 1.0 64 7.1 10.3 3.2 67 7.0 11.9 4.9 70 8.3 13.0 4.7 77 9.6 25.7 16.1 88 10.4 25.1 14.7 89 10.5 14.4 3.9 90 17.7 26.9 9.2 91 9.9 23.2 13.3 92 10.3 12.9 2.6 94 11.1 13.4 2.3 95 17.7 27.5 9.8 96 10.1 21.7 11.6 98 10.6 27.6 17.0 V-l 11.9 16.8 4.9 89 Table 2 Identification of antagonistic bacteria against Erwinia carotovora subsp. atroceptica Isolate No. Antagonistic bacteria Source of isolation 10 Bacillus sphaericus soil 43 Bacillus subtilis seed compost (1) 51 Bacillus brevis seed compost (1) 58 Bacillus subtilis seed compost (1) 64 Bacillus subtilis seed compost (1) 67 Bacillus subtilis seed compost (1) 70 Bacillus subtilis seed compost (1) 77 Bacillus polymyxa seed compost (2) 88 Bacillus polymyxa seed compost (2) 89 Bacillus sphaericus seed compost (2) 90 Bacillus circulans seed compost (2) 91 Bacillus polymyxa seed compost (2) 92 Bacillus sphaericus seed compost (2) 94 Bacillus sphaericus seed compost (2) 95 Bacillus polymyxa seed compost (2) 96 Bacillus polymyxa seed compost (2) 98 Bacillus polymyxa seed compost (2) V-1 Pseudomonas vesicularis soil (1): Produced by Division of Soil and Water Conservation, Department of Land Development (2): Commercial seed compost 90 TH9900011 TH9900011 Bactrocera dorsalis (Hendel)YlfnEmfhfi'mmi ??-mfU'mvia-j>niiibxnajmetfufl WWJ nnui 10900 1Y)5 5795230 fit! 571 Bactrocera dorsalis (Hendel) W{1fn7'MPia0-4y Studies on mating competitiveness of sterile oriental fruit fly, Bactrocera dorsalis (Hendel) Wanit Limohpasmanee and Suchada Segsarnviriya Biological Science Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok 10900 Tel. 579-5230 Ext. 571 Fax. 561-3013 ABSTRACT An essential prerequisite for insect control by the sterile insect technique releasing method is mass rearing and sterilizing that do not have adverse effects on longevity and mating behavior of the released males. But many laboratory studies have shown that males irradiated at the completely sterility dose often could not compete with untreated males in mating. This paper studies the effects of gamma radiation at the sterile dose on mating, sexual and sperm competitiveness of the oriental fruit fly, Bactrocera dorsalis (Hendel) under the laboratory condition. It is found that irradiation at the completely sterility dose (90 Gy) had reduced the mating and sperm competition ability of the males. Though the sexual competition was not 91 INTRODUCTION An essential prerequisite for successful application of the sterile insect technique release method to eradicate or control the insect pests is mass rearing and sterilization that do not have adverse effects on longevity and mating behavior of the released males. Many laboratory studies have shown that males irradiated with gamma radiation at the completely sterile dose often could not compete with untreated males in mating although irradiation did not significantly reduce longevity of the males (Economopoulos, 1972). In addition, mass rearing of insects at the constant temperature and using artificial diet for many generation effect on physiological and behavioral characteristics . Kakinohana (1980) reported that mass rearing with artificial diet in laboratory caused the qualitative changes of the melon fly, such as oviposition, sexual maturation, diurnal rhythm of mating, mating competitiveness and dispersal ability in the field. The experiment of Hibino and Iwahashi (1989) showed the difference of mating behavior between mass reared melon fly and wild fly. Iwahashi (1992) showed the results of SIT at Doi Ang Khang, a part of Integrated Control of Fruit Flies which supported by IAEA. Though the number of released flies per month reached 30 millions and the M/U ratio reached 10 or more, the number of wild flies caught from traps did not decreased, so ratio of M/U did not increase. The fault of the control may be occurred because of the low quality of the raleased flies or the immigation of wild flies. Iwahashi (1993) showed the non-synconized daily activity pattern with wild flies of the released flies. Mating and sexual competitiveness are the method that can be used as a quality control of the flies to check results from mass rearing, irradiation and transportation. However, the mating and sexual competitiveness data in laboratory is not realized under the field conditions. This paper studies the effects of gamma radiation at the completely sterile dose on mating, sperm and sexual competitiveness of the oriental fruit fly, Bactrocera dorsalis (Hendel) under the laboratory condition. MATERIAL AND METHODS Insects: The oriental fruit fly, Bactrocera dorsalis (Hendel) used in this experiment were taken from the mass rearing facility of OAEP (Office of Atomic Energy for Peace).The 2 days before emergence pupae were marked and irradiated with gamma radiation at the dose of 90 Gy at TIC (Thai Irradiation Center ). After emergence 2 days, both normal and irradiated flies were sexed 92 and reared separately in laboratory at temperature 27 ± 2 °c with water and the mixture of sugar and protein yeast hydrolysate. The 4-day-old flies were treated with cool and marked individually with enamel paint pens. Cages: The 25x25x25 cm. screen cages were used to study the mating and sexual competition of the flies. The plastic containers, with 6 cm. diameter and 10 cm. height , were used to study sperm competition of the flies. Water and the mixture of sugar and protein yeast hydrolysate were provided. Experiments To study the mating and sexual competitiveness tests, the marked flies were put in the cages as shown in Table 1. Table 1 The combination of normal and irradiated males and females in each treatments Treatment Combination Normal male Irradiated male Normal female 1 30 0 15 2 20 10 15 3 15 15 15 4 10 20 15 5 0 15 30 After fly releasing, the cages were kept in laboratory at temperature 27+2 °c, under the natural light condition. The number of mating flies were checked and identified every day until none mating. The egg collection by using guava juice stimulation were done twice a week. To study the sperm competition, the virgin females were mated separately to normal males and to irradiated males after eclosion 10 days. After the successful copulation had occurred, all males were removed the morning after. On the third day after the first copulation, the virgin normal and irradiated males were put into the cages, for the remating of the females with opposite type males from the first mating. The eggs collected from successful remating females were checked hatchability every two days. 93 RESULTS AND DISCUSSION Table 2 shows the number of mating of normal and irradiated males in each treatments and competitiveness values, estimated directly from the number of mating flies ( Teruya and Sukeyama, 1979). C= (i/u)/(I/U) C = competitiveness value i = number of mated irradiated males u = number of mated normal males I = number of irradiated males U = number of normal males Table 2 The number of mating of normal and irradiated males and competitiveness values in different ratio of normal and irradiated males Female Ratio of No. of No. of mated No. of mated C I/U copulation normal male irradiated male N 0:30 9 9 0 N 10:20 15 12 3 0.50 N 15:15 13 10 3 0.30 N 20:10 16 4 12 1.50 N 30:0 14 0 14 The result shows that the number of mating normal males was slightly higher than irradiated males (C = 0.77+0.64). The number of mating normal male per irradiated male and competitiveness values at the ratio of irradiated per normal male 10/20, 15/15 and 20/10 when mated with normal females were 12:3, 10:3, 4:12 and 0.5, 0.3, 1.5 respectively. At the higher ratio of irradiated per normal males, competitiveness value was higher. 94 Mating (time) Fig. 1 Mating frequency of normal and irradiated oriental fruit flies The mating frequency of normal and irradiated males are shown in Fig.l , that irradiated males could mate more frequency than normal males (xn = 1.44, xir = 1.57) but non significance at level p = 0.05 (t = 0.478). The percentage of non- mating of normal and irradiated males were 69.33 and 69.33 % and percentage of normal and irradiated males mated more than 1 time were 9.33 and 10.67 %, while the percentage of mating of normal females more than 1 time was 24 %. Table 3 The estimation of the sexual competitiveness of sterile Bactrocera dorsalis (Hendel) under laboratory condition Combination Total no. of No. of egg % Egg hatch C SM NM[ NF flies examined 0 30 15 45 1017 80.02 10 20 15 45 2206 32.49 2.93 15 15 15 45 1691 11.74 5.82 20 10 15 45 1673 54.16 0.24 30 0 15 45 1977 0.00 Note : SM = Sterile males NM:= Normal males NF =: Normal females 95 The result shows that irradiated males were stronger than normal males (C = 3.00 ± 2.79). At the ratio of normal per irradiated males 20/10, 15/15 and 10/20, the sexual competitiveness values were 2.93, 5.82 and 0.24 respectively. At the ratio of normal per irradiated males 20/10 and 15/15, the sexual competitiveness were higher than the mating competition due to prior mating of irradiated males and the most of females mated only one time. But at the ratio of normal per irradiated male 10/20, the sexual competitiveness was low although the mating competition was not low. It is because the most of females remated with normal flies and the sperms from irradiated males were weaker than those from the normal males (Table 4). Table 4. Mean hatchability and P2 values of eggs laid by the female oriental fruit flies during 30 days after the second mating in double-mating schedules. Treatment No. of females % hatchabihry P2 Mean N 50 80.02 S 50 0.00 NS 15 41.06 0.6570 0.5656 SN 22 52.57 0.4869 Note : N = Females mated with normal males S = Females mated with sterile males NS = Females mated with normal and sterile males SN = Females mated with sterile and normal males P2 value was calculated by transforming formula of Boorman and Parker (1976) as follow: P = (x-b)/(a-b) where a, b, and x are the hatchability of eggs from mating with a normal male, that from mating with a irradiated male, and that from mating with both normal and irradiated males, respectively. When the second male is normal, P2= P, and when the second male is irradiated, P2 = 1-P. Hatchability and P2 values were transformed to arcsin-square roots to normalize them and unweighted means. 96 The result shows that sperms of the irradiated males were weaker than those of normal males (P2 = 0.5656). However, the result is not different from the melon fly, Bactrocera cucurbitae which P2 is nearly 0.5 (Tsubaki and Sokei, 1988). These results also indicate that irradiation with the completely sterility dose (90 Gy) had reduced mating and sperm competition ability of the flies. Though the sexual competition was not reduced, due to the earlier mating of the irradiated flies and almost females mate only one time. REFERENCES 1. Boorman, E. and G.A. Parker (1976) Sperm (ejaculate) competition in Drosophila elanogaster, and the reproductive value of females to males in relation to female age and mating status. Ecol. Ent. 1: 145-155. 2. Economopoulos, A.P. (1972) Sexual competitiveness of y-ray sterilized males of Dacus oleae. Mating frequency of artificially reared and wild females. Env. Ent., 1: 490-497. 3. Hibino, Y. and O. Iwahashi (1989) Mating receptivity of wild type females for wild type males and mass-reared males in the melon fly, Dacus cucurbitae Coquillett (Diptera: Tephritidae). Appl. Ent. Zool., 24: 152-154. 4. Iwahashi, O. (1992) THE END-OF-MISSION REPORT FOR THA/5/038/02. IAEA. 43P. 5. Iwahashi, O. (1993) FOLLOW-UP-MISSION REPORT FOR THA/5/038/02. IAEA. 33p. 6. Kakinohana, H. (1980) Qualitative change in the mass reared melon fly, Dacus cucurbitae Coq. Proceedings of a Symposium on Fruit Fly Problems. Kyoto and Naha. Japan. : 27-36. 7. Teruya, T. and H. Sukeyama (1979) Sterilization of the melon fly, Dacus cwcurMaeCoquillett, with gamma radiation : Effect of dose on competitiveness of irradiated males. Appl. Ent. Zool., 14:241-244. 8. Tsubaki, Y. and Y. Sokei (1988) Prolonged mating in the melon fly, Dacus cucurbitae Coquillett (Diptera: Tephritidae): Competition for fertilization by sperm-loading. Res. Popul. Ecol. 30:343-352. TH9900012 TH9900012 nrn ne^yitnfrW 6 ii ^0 Seber's, Jolly-Seber's, Jackson's, Ito's, Hamada's ims Yamamura's method h mnr Population Estimation with Mark and Recapture Method Program Wanitch Limohpasmanee and Pravait Kaewchoung Biological Science Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok 10900 Tel. 5795230 Ext. 571 ABSTRACT Population estimation is the important information which required for the insect control planning especially the controlling with SIT. Moreover, It can be used to evaluate the efficiency of controlling method. Due to the complexity of calculation, the population estimation with mark and recapture methods were not used widely. So that, this program is developed with Qbasic on the purpose to make it accuracy and easier. The program evaluation consists with 6 methods; follow Seber's , Jolly-seber's, Jackson's, Ito's, Hamada's and yamamura's methods. The results are compared with the original methods, found that they are accuracy and more easier to applied. 98 INTRODUCTION The basic information such as life cycle, behavior, dispersal, population density, damaging of insect pest are prerequired for planning insect control. Especially, the insect controlling with sterile insect technique, number of released flies bases on the number of flies in the nature. By the general, number of released flies must be more than 10 time number of natural flies. Moreover, the population density can be used to evaluate directly the efficacy of controlling method by comparison between before and after control application. It is better than the indirect evaluation which evaluate from damage or ratio of marked flies per unmarked flies. To know the insect population density, can count directly in the case of insect which have not high dispersal. But in the case of insect which have high dispersal, the population density can be estimated indirectly from their damage , faeces or trapping data. However, the relationship between the number of insects and number of damage or faeces or trapped insect must be known before. Moreover, the efficacy of trapping varied with many factors such as host plant, temperature, humidity and location of traps. So that, the population estimation with mark and recapture methods were developed. Due to complexity of estimation with mark and recapture methods, they were not used widely. Thought, it's accuracy is higher than another methods in the case of highly distributed insect. The population estimation with mark and recapture method program is developed with Qbasic on the purpose to make it accuracy and easier. The development of population estimation with mark and recapture methods In 1930, Lincoln presented lincoln index, based on assumption that ratio of cathed marks equal ratio of catched nature flies m / Mo = u / NL(0) N no) =Mou/m In 1939, Jackson presented "positive method" based on assumption that 100 marked individuals are released on the initial day and 100 random samples are caught on the i day. y; = 10 nr /Monj 4 No= 10 /y0 99 In 1959 Darroch presented " capture-recapture analysis" , shows that in a fully stochastic model with either immigration (often called dilution) or death (or emigration), the population parameters can be easily estimated by maximum likelihood. For the more general case when death and immigration are operating simultaneously he derives estimation equations by equating certain observations to their expectations, but does not give variances or covariances for the estimates. In a leter paper, (Darroch, 1961), he considers estimation for a closed population consisting of different strata. In 1962 Seber presented "multi-sample single recapture method" ,which an individual cannot be recaptured more than once. This situation arises, for example, when the recaptures are made in the course of hunting or fishing. He allows for both death and immigration in the population, provides explicit maximum-likelihood estimates of the parameters with variances, and suggests tests for certain of the assumptions. In 1965 Jolly presented "Explicit estimates from capture-recapture data with both death and immigration-stochastic model" for a population in which there is both immigration and death, provides explicit maximum-likelihood estimates of the parameters with variances and means. In 1965 Seber presented "A note on the multiple-recapture census" , the method of solution is similar to that given in Jolly (1965) In 1973 Ito presented "A method to estimate a minimum population density with a single recapture census" based on Jackson's positive method using data from a single release and repeated recapture samplings. He stated that there was negative bias inherent in his system influenced by rates of survival and capture. M^ = Mo- Zj^m, 4 /M n yj+1 = 10 mi+, o 4 No = 10 /y0 In 1976 Hamada presented "Density estimation by the modified Jackson's method" based on Jackson's and Ito's methods z, = K/nr/M,,^ 4 No = 10 /z'0 ioo In 1992 Yamamura presented " A method for population estimation from a single release experiment " based on Seber's method (1962), but sampling censuses are conducted only twice. A (|) = (u.iV u2m,)+ m,/ Mo A A U = (|> Mo u, / m, METHOD The operation of population estimation with mark and recapture method program The operation of this program is devided into 3 sections as follows: l.Data Base on releasing and recapture census, data are classified to 3 groups : 1.1 Multiple release census This data are suitable to calculated insect population in the opened area which there are both immigration and emigration with Seber's or Jolly-Seber's method. The captured individuals are removed or killed in Seber's method but the captured individuals are released without hazard in Jolly-Seber's method. The data must be inputed step by step as follows: - Inkey " How many time individuals are released" - Inkey " Number of released individuals in each time" - Inkey " Number of unmarked in each samples" - Inkey "Number of the first released individuals in each samples" - Inkey " Number of the individuals which released at time i in each samples" - Inkey " Total number of catched individuals in each sample" only Jolly-Seber 's method 1.2 Single release and multiple recapture census This data are suitable to calculate the insect population in the closed area which there are not immigration and emigration, number of insect is constant which data are collected, with Jackson's or Ito's or Hamada's method. The catched individuals are removed or killed. The data must be inputed step by step as follows - Inkey " Only 1 time, individuals are released " 101 - Inkey " How many times, samples are taken" - Inkey " Number of released Individuals" - Inkey " Number of catched individuals in each samples" - Inkey " Number of catched unmarked individuals in each samples" - Inkey " Number of catched marked individuals in each samples" 1.3 Single release and twice recapture census This data are suitable to calculated insect population in the opened area which there are both immigration and emigration with Yamamura's method . This method is similar Seber's method, but the samples of insects are taken only twice. The data must be inputed step by step as follows - Inkey " Only 1 time, individuals are released " - Inkey " Only twice, individuals are recapture" - Inkey " How many replication are done" - Inkey " Number of released individuals in each replication" - Inkey " Number of unmarked individuals in the first sample of each replication" - Inkey " Number of marked individuals in the first sample of each replication" - Inkey " Number of unmarked individuals in the second sample of each replication" - Inkey " Number of marked individuals in the sercond sample of each replication" 2. Evaluation There are 6 calcualtion methods, so that user must choose the calculation method which match with the data group. 2.1 Seber's method The program will calculate data step by step as follows: 2.1.1 Recapture Rate (Q*{) A 2.1.2 Probability of survival ((f)^), probability of being caught ( p: ) A and total number of population ( nf ) Xh %4i / X51 ai (V =<|>,Aq,A 102 &,© si X2. n,A = u, /p A While ^ = Total number of marked individuals belonging to a,, a^ ....a, which are caught after the sample b; is taken %2i = The number of marked individuals belonging to ai+1 which are caught during the whole experiment %3i = The number of marked individuals in b, yAi = The number of marked individuals belonging to a, which are caught during the whole experiment Xli ~~ Xli A*3i A 2.1.3 Variance of (p*, P. and n/ 2 2 var(l/pi*) = q, /Pi {1/SH+ 1/c2i- k = A,: (*. 2 ^., +l/8 -l/a ] var((|),*) = qs-,) 1 + i/ 4s s var ( n * ) = ( e*= (Oi/ai)e3i 2.2 Jolly-Seber stochastic method The program will calculate data step by step as follows: A 2.2.1 Total number of marked individuals at risk in the population on the sampling day (Mj ) and The poportion of marked individuals in the population at the moment of capture on day i ( a,) While a = Total number of released individuals on day i 103 Tj = Total number of marked individauls recapture on day i n: = Total number captured on day i Rj = Total number of individuals released on the i occasion, subsequently recaptured Z; = The number marked before time i which are not caught in the i sample, but are caught subsequently A 2.2.2 The estimated of population on day i (N( ), probability that an individual alive at moment of release of the i sample will survive till the time of capture of the i+1 sample ( (|)A ) and The number of new individuals joining the population in the interval between the i and i+1 samples and alive at time i+1 ( BA) A A = M j+l/(M -r, +at ) A A A B = N +l - (j)* ( n - n, + a,) A A A A 2.2.3 Variance of N, , Nf /N{, (|) and var(N,A) = N^CN^-n^ A A A A var (N, /N;) = N, (Ns -n(){ [(M, -rs +a: var r+1 +ai+ A A + (M, -r, )/(M, -r| +&i Kl/Rj -1 A 2 var ( ^ /,)= var «|> ) - [(|). ( 1 - (J),)/ M1+1] 2.3 Jackson's method The program will calculate data step by step as follows: 2.3.1 Converted value of mi (yj) 4 y; = 10 m; /a Mo A 2.3.2 Estimated value of y{ at time i (y0 ) and survival rate ( S) from the regression line of i and log y: logy, = Iogy0 + i log S 2.3.3 Total number of wild individauls (U) A 4 A N = 10 /y0 U = N - Mn 104 2.4 Ito' s method The program will calculate data step by step as follows: 2.4.1 Converted value of m: (y^) NV=M0- Zj.rx 4 y,'= 10 m,/niM0(i) A 2.4.2 Estimated value of y;' at time 0 (yo' ) and survival rate ( S) from regression line of i and log y:' log y^ = log y0' + i log S 2.4.3 Total number of wild individauls (U) A 4 A N, = 10 /y0' U = N - Mo 2.5 Hamada's method The program will calculate data step by step as follows: 2.5.1 Converted value of m, (z^) M = M «i)' o • Xh,' ' nij 4 Zj' = 10 m. / u, MWi) A 2.5.2 Estimated value of z' at time 0 ( zo' ) and survival rate ( S) from regression line of i and log z' log Zj' = log z0' + i log S 2.5.3 Total number of wild individuals (UA) A 4 A U = 10 /z0' 2.6 Yamamura's method The program will calculate data step by step as follows: 2.6.1 Proportion of marked individuals which survive and stay in the population between the successive censuses ( ^i), wild population size ( LT ) (j)( = (u, n^ / m, 112) + m, / Mo U,= 2.6.2 Mean of (j), and Uj 1/k 105 2.6.3 Variance of (j) and U 2 var «j)) = {(1/MO) - [(m, + u,)m2 / (m, 'u2) ]} var (m, ) + {(m2 + u2)u, / (u2 m, )} var(m2) 3 2 var (U) = {2M0 u, [(m, + u,)m2 / (m, u2) ] +1 } var (m, ) + {Mou, (m2 + u2) / (u2 m, )} var(m2) While varOn,) = (U - u^^m, /U^ + mJ 3. Display The program will show the results on the monitor after the calculation and the results will be printed if print order in the menu are chosen. Moreover, all data can storaged on disc by using Qbasic menu. Example Population estimation of the oriental fruit fly at Pakchong District, Nakornrachasema Province, 23 January- 4 March 1997 Jackson's Positive Method (1939) Time Mo n u m 1 3673 557 454 103 2 3570 349 244 105 3 3465 286 230 54 4 3411 171 160 11 5 3400 299 268 31 6 3369 128 123 5 Wild population = 5620.31 Recapture rate = 8.412742 >;10'2 Survival rate = 0.7086537 RESULTS Coparison results with original methods 1. Seber's method (1962) The population estimation of male,Spodoptera litura (Fabricius) at Kagawa Prefecture, Northern Shikoku, Japan in May-September (Wakamura et al., 1990). 106 Results of Calculation follow Seber's method (1962) ! v : Dale M, ">, u. u- V(U")' U, "i «fc>" Jun 16 1934 383 26 181 24 93.22 0.710 30.08 0.129 17 1968 428 24 137 20 66.39 0.602 1992 0.099 IK 2259 500 211 201 17 62.73 0694 2175 0.134 19 1098 215 17 73 11 62.56 0 721 2659 0.189 avg. 7122 0680 12.45 0.069 Jul 15 764 181 BO 26 65 139.70 0.414 18.39 0.031 16 2226 466 65 121 59 153.82 0.495 26.08 0.044 17 1770 420 59 76 60 103.24 0.415 13.69 0.024 IVg. 132.25 0.440 11.57 0.019 Results of calculation with program Dale M, m, u, m, u, U" *," V(U-)" Jun |6 1934 383 26 181 24 93.22 0710 30.08 0.129 17 1968 428 24 137 20 66.39 0602 19.92 0.099 18 2259 500 20 201 17 6273 0.694 21.75 0 134 19 1098 215 17 73 11 62.56 0.721 26.59 0 189 avg. 71.22 0.680 12.45 0.069 Jul 15 764 181 80 26 65 139 70 0.414 18.39 0 031 16 2226 466 65 121 59 153.82 0.495 26.08 0.044 17 1770 420 59 76 60 103.24 0.4)5 13.69 0.024 avg. 132.25 0.44O 11.57 0.019 2. Jolly-Seber stochastic method (1965) Jolly's experiment (1963), estimated population of female black-kneed capsid {Blepharidopterus angulatus) in apple orchard, in which dilution both by fresh emergences and by immigration was occurring. Table 3 Result s of calculation follow Jolly-Seber stochastic method (1965) l: n = 1 a- M," N," {V(N,")|'" (V«j),~l) (V(N,"/N,)| (Vtcf), ".' <(>. )l' 1 0 0.649 0.114 0.093 2 0.0685 35.02 5112 1.1015 151 2 0.110 150.8 0.110 3 0.2189 170.54 779 1 0.867 1293 0.107 128.9 0.105 4 0.2679 258.00 963.0 0.564 140.9 0.064 140 3 0.059 5 0.2409 227.73 945.3 0.836 125.5 0.075 124.3 0.073 6 0.3684 324.99 882.2 0.790 96.1 0.070 94.4 0.068 7 04480 359.50 802.5 0.651 74.8 0.056 72.4 0.052 8 0 4886 319.33 653.6 0.985 61.7 0093 58.9 0.093 9 0 6395 402.13 628.8 0.686 61.9 0.080 59.1 0.077 10 0.6614 316.45 478.5 0.884 51.8 0.120 48.9 0.118 11 0.6260 317.00 506.4 0.771 65.8 0.128 63.7 0.126 12 0.6000 277.71 462.8 70.2 68.4 13 06690 107 ?le 4 Results of calculation with program N l! A J a/ M," ," (V(N,")|" IV«t>,")l" {V(N,"/N,))' (V( 2 0.0685 35.02 511.2 1.1015 151.2 0 110 150.8 0 110 3 0.2189 170.54 779.1 0.867 129.3 0.107 128.9 0 105 4 0.2679 258.00 963.0 0.564 140.9 0 064 140 3 0059 5 0.24O9 227.7] 945] 0.836 125.5 0.075 124.3 6 03684 324.99 882.2 0.790 96 1 0.070 94.4 0.068 7 0.4480 359.50 802.5 0.651 74.8 0.056 72.4 0.052 8 0.4886 319.33 653.6 0.985 61.7 0093 58.9 0.093 9 0.6395 402.13 628.8 0.686 61.9 0.080 59.1 0.077 10 0.6614 316.45 478.5 0.884 51.8 0.120 48.9 0.118 II 0.6260 317.00 506.4 0.771 65.8 0.128 63.7 0.126 12 0.6000 277.71 462.B 70.2 68.4 1} 0.6690 3. Jackson's method Experiment of Ito et al. (1974), estimated the population of Dacus cucurbitae in Kume Island , Oct. - Nov. 1972 - Results of calculation follow Jackson's method Total number of Dacus cucurbitae = 2416.81 PH Survival rate = 0.65305034 Recapture rate = 0.062780269 - Results of calculation with program Total number of Dacus cucurbitae =2416.81 fll Survival rate = 0.65305034 Recapture rate = 0.062780269 4. Ito's method Experiment of Ito et al. (1974) estimated population of Dacus cucurbitae in Ishigaki Island , June-July 1973 108 it© jle 5 Results of calculation follow Ito's method parameters Station C (4 ha) Station D (2 ha) Red Blue White Blue N1(0, 2092 487 623 negative N,(1, 0.408 0.436 0.443 0.396 N 983 480 J(.) 0.277 0.428 Table 6 Results of calculation with program parameters Station C (4 ha) Station D (2 ha) Red Blue White Blue 2092 487 N«o, He.) 623 negative * 0.408 0.436 0.443 0.396 983 480 NJ(,» 0.277 0.428 5. Hamada's method Experiment of Ito et al. (1974) estimated population of Dacus cucurbitae in Ishigaki Island, June-July 1973 109 Table 7 Results of calculation follow Hamada's method parameters Station C (4 ha) Station D (2 ha) Red Blue White Blue uA 131 127 A 1228 483 U 0 610 Uo, 1359 UA, 1091 397 u, 1222 524 R 0.0963 0.1072 0.2081 0.2423 S(l-R) 0.2040 0.3637 0.2520 0.3047 S 0.2258 0.4073 0.3182 0.4034 Results of calculation with program parameters Station C (4 ha) Station D (2 ha) Red Blue White Blue uA 131 127 A 1228 483 U 0 610 Uo, 1359 UA, 1091 397 u, 1222 524 R 0.0963 0.1072 0.2081 0.2423 S(l-R) 0.2040 0.3637 0.2520 0.3047 S 0.2258 0.4073 0.3182 0.4034 6. Yamamura's method Experiment of Wakamura et al.(1990), estimated population of males, Spodoptera litura (Fabricius) at Kagawa Prefecture, Northern Shikoku, Japan in May- September. 110 jle 9 Results of calculation follow Yamamura's method v : DIM M, m, IT V(U")'" u, u: «t>,- «t>.>' Jun 16 1934 383 26 181 24 93.22 0.710 30.08 0.129 17 1968 428 24 137 20 66.39 0.602 1992 0.099 18 2259 500 20 201 17 62.73 0694 21 75 0.134 19 1098 215 17 73 11 62.56 0721 26.59 0.189 avg. 71 22 0680 12.45 0069 Jul 15 764 181 80 26 65 139.70 0.414 18.39 0.031 16 2226 466 65 121 59 153.82 0.495 26.08 0.044 17 1770 420 59 76 60 103.24 0.415 13.69 0024 avg. 13225 0.440 11.57 0 019 Table 10 Results of calculation with program ! v Dite M, ™, u, m, u. V *," V(U")' «t\l" Jun 16 1934 383 26 181 24 93.22 0.710 30.08 0.129 17 1968 428 24 137 20 66.39 0.602 19.92 0.099 18 2259 500 20 201 17 62.73 0.694 21 75 0.134 19 1098 215 17 73 11 62.56 0.721 26.59 0.189 avg. 71.22 0680 12.45 0.069 Jul 15 764 IB! 80 26 65 139.70 0.414 18.39 0.031 16 2226 466 65 121 59 153.82 0.495 26.08 0044 17 1770 420 59 76 60 10324 0.415 13.69 0 024 ivg 132 25 0.440 11.57 [1019 SUMMARY This program can be applied to estimate insect population in both opened area (there are both immigration and emigration ) and closed area (population density is constant). The results are accuracy, when compared with the original methods but it is easier and quickly to use this program. However, the user must have the basic in the field of ecology so that he can plan which method is suitable for his study case. REFRENCES 'u .niii?(ju1iJianiufn%Ji Basic. . 2533.310 M. , f1?^m"VNc1. 2533. 136 U. 111 STlffa, fli-NYmi. 2533. 197 14. Ageloff, R. and R. Mqjena. Applied Basic Programming. Wadsworth Pulishing Company, Belmont, California. U.S.A. 1980. 352 pp. Hamada, R., Density Estimation by the Modified Jackson's Method. Appl. Ent. Zool. II (3). 1976.194-201. Ito ,Y. A method to estimate a minimum population density with a single recapture census. Res. Popul. Ecol. 141973. 159-168. Ito, Y. , M. Murai, T. Teruya, R. Hamada and A. Sugimoto. An estimation of population density of Dacus cucurbitae with mark-recapture methods. Res. Popul. Ecol. 15 1974. 213-222. Jolly, G.M. Explicit estimates from capture-recapture data with both death and immigration- stochastic model. Biometrika 52, 1 and 2 1965. 225-247. Kemeny, J.G. and T. E. Kurtz . Basic Programming . John Wiley & Sons, Inc., New York, U.S.A. 1968. 122 p. Seber, G. A. F. The multi-sample single recapture census. Biometrika 49, 3 and 4 1962. 339- 350. Seber, G. A. F. A note on the multiple-recapture census. Biometrika 52, 1 and 2 1965. 249-259. Seber, G. A. F. The effects of trap response on tag recapture estimates. Biometrics, March 1970. 13-22. Yamamura, K., S. Wakamura and S. Kozai. A method for population estimation from a single release experiment. Appl. Ent. Zool. 27 (1) 1992. 9-17. (B) TH9900013 TH9900013 115 t eiffitj? 01101 aju oVnfVm fltu:nninfnflfli fa n^mvii 10520 Beta ims ZSM-II Polymerization of Polyacrylonitrile within Zeolite Micropores Tawan Sooknoi, Artit Ausavasukhi, Wischalee Setasuntorn, Araya Kittivanichawat and Theerawat Mongkolaussavarat Zeolite and Micropore Materials Research Laboratory, Department of Chemistry , Faculty of Science, King Mongkut's Institute of Technology Ladkrabang, Chalongkrung Rd., Ladkrabang, Bangkok 10520 Polyacrylonitrile can be synthesized within the micropores of zeolites Beta and ZSM-11 by irradiating gamma ray to the zeolites, on which acrylonitrile monomer was already adsorbed. Alternatively, it can be carried out by heating such zeolites which have impregnated azobisisobutyronitrile as initiator. The resultant composite was analyzed using Thermo Gravimetric Analysis, Differential Scanning Calorimetry and Fourier Transform Infrared Spectroscopy. It was found that framework topology, particularly the pore size limitation, strongly effects polymerization reaction and also thermal degradation behavior of the polymer formed. 116 urmi (composite material) (matrix) lflul&m9UlJYliMlllJfT'n«'3imJ (filler) 1980s Thomas Bein Uf\t Patricia Enzel'" ift'Mlfni^lfl^iSlMViealvilin (Polypyrrole) fnu1\4§1o1n>l Y HH£ Mordenite ^S Fe3+ Vffo Cu2+ Patricia Enzel, Joshph J. Zoller UQZ Thomas Bein(2) M' Y ims Mordenite (Pyroiysis) VlQfl'OifnT'U Patricia Enzelims Thomas Bein0) NaY Na-mordenite (Aqueous solution) Beta ims; ZSM-II (7-8 Q^ttwiou) imsnfn-3 (5-6 Q^ff^ieu) wiuanwu 2 uuu 117 l. Beta uas ZSM-II Beta 30.0SiO2 : 1.0Al2O3 lO^Na/) : 6.0TEAOH : 250.0 H20 40 iiWwiiw TiwwuofjSaifl (37.57 % 59.54% Al2o3) 40 nJoiwvm (Ludox AS40) ua 160 0-3ffni«Kcii§fjff iilunm 10 TU<4) ^ ZSM-ll 149.7SiO2: 1.0Al2O3 : 16.5Na2O : 18.9TBABr : 4096.9 H2O < < (37.57 % NajO, 59.54 % A12O3) tt1?3^in£JU UTU?1O(J«5afnt llU'll\4 40 (Ludox AS40) h 150 i iilunm 88 ihluV51 (SEM) (XRD) ims 2. 50 5fi«nfjjlfrlunao«vi9i?i9-3ploi Manifold) 30 uivi 15 5anS?ii'U7iio1i4iiao^vififio-j(pionuyi0^Rjtyimff (seal) 12.5 uas 20 nlnmio 118 100 70 3. i9u,m 4. 4.1 li (Thermo Gravimetri Analysis, TGA) 20 Snanfu uii^lvj^n^wiQiln (Pt pan) 20 mmmt\)3usm?iw-\r\ imsflg^nmii'HJiiig^nTuiul^iiflV! 50 mil'Hfmul'0'u1v4 ]15i (Differential Scanning Calorimetry, DSC) 5-10 £maniu ai'HrS 20 350 o^ffii'Km^tJtT imsew^ifniapifmiJiDU 20 40 50 i 4.3 nTSWIlfltrO'Uniigplfia'WUa^lEJinn'Wflm'SgfinaWTJaB'M^ni'Sei (Fourier Transform Infrared Spectrophotometry, FTIR) 2-3 waSnfjjjJiD^iQunulwunm^tijjIuiijJw (KBr) i 0.1 niu na'jifffi'jluim'wij'w tfnmifiig-a&mwfl^imi^fru 5xio3 3200-1200 cm"' 119 4.4 nnu 300 vwu l uasi T~T A / 1.2 Jllfl 1.3 lw l.i) Beta 120 qamQSvHnflfmnJStiinnJjM PAN/BETA PAN/ZSM-11 PAN if-KYi 1 70 68 lojuJnuviuilcn 1H-3Y12 "bJiiJacniuiJm 180 68-70 owwrarotm (iiw l) V 2) ZSM-II Beta Oflmfm 171-180 290-320 3) Beta fls; ZSM-1 s 3 2 uas 3 Beta ZSM-11 Beta Sfhinnfni 100 X. • *r-^' i 80 i if • >. -,, , IS • I'AN/m: i A t 60 ! Ivilfisiavi PAN/ZSM-I 11 ;> 40 : I omipi 10 BEEgj it :L" if A I 1*2* * 20 • mIT* 1 1 I 0 m1 12.5 Kgys 20Kgys AIHN I'AN/BETA PAN//.SM-II 12.5 121 ' 212.7 j I / A 171 ) 215.5 -1!«74J J<7.!27 1111 HI 1H 2-10 2«0 4.1) BetaQdvi 4.2) ZSM-I l (JIIYI 4.3) jilvi 4.1 vni'iiSminJ^tJ'uuiJa-jyn-jfmul'gu 2 V g (175.3 (282.7 e-jmi^ai^jJir Beta uns ZSM-11 (fl^jiJ^ 4.2-4.3) (DMF) (3200 cm'1) (c=c) 122 loavlu (1650 cm (vibration energy) (C-H stretching) IJQWIQaOSflllallj'lwimmi!: (2939 cm'') Ufl T'Beta (2940 cm"') 2fhehfmlvi§If)l'lain ZSM-11 (2948 cm"') IFS28 BRUKER AMtt fflSCHE M6SSTECMNIK GI.1BH 'I / •1 PAN/ZSM-ll 1 1 : 1- 1 1 1 • -i • •i.i ••••!:: .-•:•• i"•• -!)• ;.;:. jut :ui itx TUC .,co rtf. H ..»•.••- rj. -y BRUKER (ALYTISCH ICCOQ '•• - "SSSrECHMIKQWBH PAN'/SMI 1 ~-^/ ~\ 1 I i 1 1 1 1 1 1 1 1 ifiVbiinfllJgniinfminfnS (Cyclisation) (Ladder Polymer) lll'UWalmilii'u'Wa (mUfimJlbsUifil 2240 cm (2900-3000 cm'') 123 snn emuvi l i^ l (ibsuifu 70 2 (itasinoi 180 \ ZSM-11 Ds;tTfnt)^m9nfifmjjm1tJPiluIymn?i (molecular constraint) ZSM-II luiifus^'HaHgsjminiyifiiaivi^Iglfi'n Beta l lu'3migajmEJiJTHun1\4etf'3^fi imslw'Ki^qpi'nio (ibsuiaj 280-300 Beta flsiinfimiiTaifj^^awHfiC^in'iTWQagsfiilfiiuifiialu ZSM-II m ZSM-II wtnfifnitraitJ^figw'H'unuupiil'u^-j^fU'Hfjn 171-180 Beta 3io nas; 250 o^fmifai^tii i? (non-crystalline polyacrylonitrile) 6) 1fifjvi9a9sfii1a1i4i^?alu5l9ia'n Beta Jfnfninmu 6 e^ffwiou^ 124 Beta mflfniSlfllaii ZSM-ll (^loitl'VI Beta 7-8 04tTfl19U7 ^Toifitf ZSM-ll Swiflvie 5.4 04IYPI?91J<8)) ZSM-11 nui'mqfljvimj 900 100 I'lJoi'i'lii^lviDQis^woaosjfiilaiijlwiaiti^IoiayT'Beta ffinowiihsinai 90.94 Beta wimpi-jlMi'HU'iiinfl'HQnmafuuu^TJ'ulfiDU (in?iioiniJgmyifnim*n-3) ua 900 o-afniifmStm iTTU^Ijjfffno^ovioamoi'uuTJiilpi^tn^uu) J^ 4 m0iiJ1tJ \f\X\ Beta flsSfin4O«fll1fiiW^^1T4l0UBnil\l0-Jfn?llJat)TJUlJi1-5imUfnO'H^^l\i (-285.3 vumviQti) ffQU'HQaosfiflniu'lpiialuS'IoiaTi ZSM-I l Bs gww^^ntj (-187.2 o^frniijfii^tJtt 284.7 9-jfruimiqrtm) mdmo-3flinvioSos;fi?Iavlw'l?i5alu§ i^i^ (~ 187.2 284.7 ^ ii Beta 285.3 280-300 mown1 wu) ^?iJ^ 4 ims 6 1i12Junfu ni-180 Beta Beta i?i4^fi0i4'i(n^1'Hd'U9-3yi0§i0iti'yT' Beta fifla lu l^iaviuMij lu wia9^9iflinfi9iupi5nioifnwmjntjli!if (woaosfi?la lu (helix) u«nljjl^Smifin9tT0uniJ^«3iT4«^naT3) mi flTllwigW ZSM-I l 125 Beta (2940 cm') ZSM-I l flx ZSM-I l (2948 cm1) cm"1) (Conjugation) 7) Beta uas ZSM-11 (Degradation) Beta mn^Tu ZSM-I 1 T C Adsorpmn 111 C N *- C C C N N N PolvmerKition Pyro lysis N N N 126 ^vi 1)0^9305; (morphology) 300 lflTH14n^^TUn-31WVia-341l4lJ?lJ1Qime^\4^l99lfl9im9^ Gamma Cell uemfl91t9UimutTO3n5nfl (Scanning Electron Microscope) 1. Bein, T. and Enzel, P., Angew. Chem. Int. Ed. Engl. 28(12), (1989) : 1692-1694. 2. Bein, T., Enzel, P. and Zoller, J. J.,7. Chem. Soc, Chem. Commun. 93, (1992): 633-635. 3. Bein, T. and Enzel, P., Chem. Mater. 4, (1992) : 819-824. 4. Smirniotis, P. G. and Ruckenstein, E., Ind. Eng. Chem. Res. 33, (1994): 800-813 5. Woodbury, N. and Chu, P., U. S. Pat 3, 709, 979, Jan. 9, 1973. 6. Brandrup, J. and Immergut, E. H., Polymer Handbook 2" ed., New York, John Willey & Son, pp. v39. 7. Treacy, M. M. J., and Newsam, J. M, Nature (London). 332, (1988) : 249 8. Fyfe, C. A., Gies, H., Kokotailo, G. T., Pasztor, C, Strobl, H. and Cox, D. E., J. Am. Chem. Soc. Ill, (1989): 2470-2474 127 a/ <( Cll VtllWU WUlflicy ffYiVVl frUYlitufil UflS George Bereznai 10330 In?:662-218-6781 Iviitni: 662-218-6770 900 100 Mfe moumi v 128 TH9900014 TH9900014 Interactive Real-time Simulation of a Nuclear Reactor Emergency Core Cooling System on a Desktop Computer Chaiwat Muncharoen, Supitcha Chanyotha and George Bereznai Nuclear Technology Department, Chulalongkorn university Phyathai road, Bangkok 10330, Thailand Tel:662-218-6781; Fax:662-2186770 Internet:[email protected] ABSTRACT The simulation of the Emergency Core Cooling System for a 900 MW nuclear power plant has been developed by using object oriented programming language. It is capable of generating code that executes in real-time on a PENTIUM 100 or equivalent personal computer. Graphical user interface ECCS screens have been developed using LabVIEW to allow interactive control of ECCS. The usual simulator functions, such as freeze, run, iterate, have been provided, and a number of malfunctions may be activated. A large pipe break near the reactor inlet header has been simulated to verify the response of the ECCS model. LOCA detection, ECC initiation, injection and recovery phased are all modeled, and give results consistent with safety analysis data for a 100% break. With stand alone ECCS simulation, the changes of flow and pressure in ECCS can be observed. The operator can study operational procedures and get used to LOCA in case of the LOCA. Practicing with malfunction, the operator will improve problem solving skills and gain a deeper comprehension of ECCS. 129 INTRODUCTION A large pipe break in primary heat transport system (PHT) in CANDU-9 nuclear power plant can cause a severe accident. As soon as the break occurs, the reactor power increases rapidly because of positive void reactivity. This increase during blowdown period is arrested by fast reactor trip . However, the heat buildup after reactor trip still continues. Due to loss of coolant in heat transport system, the fuel sheath temperature rises. Ultimately, it would induce core meltdown in the reactor. To refill the fuel channels and remove residual heat from the reactor fuel, Emergency Core Cooling System (ECCS), one of four safety systems in a CANDU-9 nuclear power plant, will be initiated after receiving Loss Of Coolant Accident (LOCA) signal. Mistakes made by human error or equipment failure in any stages of ECCS may trigger huge disaster in nuclear power plant. For example, if gas isolation valves cannot be open when LOCA signal is generated, the differential pressure between ECC and PHT is not adequate to burst rupture disks. Therefore, there is no flow to refill fuel channels. To evaluate ECC operating procedure, to observe the response of the parameters, and to improve the operator skill solving the unexpected problems, the simulation of the Emergency Core Cooling System (ECCS) in CANDU-9 nuclear power plant has been developed by using a simulation development system, CASSIM. A large break pipe near Reactor Inlet Headerl (RIH1) has been simulated. The graphic user interface has been developed as well to communicate interactively with user. SIMULATION METHOD The simulation of the emergency core cooling system, which is shown in Figure 1, for a 900 MW CANDU-9 nuclear power plant has been developed using an object oriented programming language. First, the process equipment was modeled to represent the equipment after the scope and description for ECCS has been defined. Then the hydraulic network model was built to represent the dynamic flow and pressure in the system. Figure 2 shows one example of nodal diagrams namely NHR. These two models were merged together to form a working model. After that, the control 130 system model was added to the working model. To observe the power change during the break, neutronic model was created. Moreover, thermalhydraulic model was built to observe the fuel sheath temperature. Finally, the graphical user interface screens were built with LabVIEW to display the necessary parameters; flow rate, pressure, temperature and to control any equipment by operator. Figure 3 shows ECCS user interface. Reactor Building <3as Isolation VaJvea HMt Sf fZf ExchangeraT J Recovery Reoovery Pumps J Nation valve* Pumps ump Sump Isola Figure 1 Emergency Core Cooling System'[21 COMPUTER CODE The thermalhydraulic of primary and ECCS circuits are simulated by using the computer code, CASSIM. CASSIM is made up of a dynamic linked library (DLL) of generic algorithms, 131 consisting of supporting FORTRAN subroutines. Generic software algorithms are developed corresponding to physical plant components such as a process, a logical unit, or equipment ( e.g. valve) . NHR X05 TO HEADER TO HEADER NHR N15 NHR Nil NHR NI2 NHR N13 NHR N14 NHR N10 NHR N09 NHR X03 NHR X01 NHR X04 NHR X02 NHR N19 NHR N17 NHR N08 NHR N04 NHR N23 NHR N21 NHR N02 NHR N06 NHR N07 NHR N03 NHR NO I NHR N05 NHR N22 NHR N20 NHR N18 NHR NI6 Figure 2 Nodal diagram for NHR. 132 CASSIM is a simulation development system based on three components: -CASSBASE: the database engine which is used to manage the library of generic algorithms, and to connect the blocks in a model together. Moreover, it is also used to manage the hydraulic flow networks. Figure 3 ECCS user interface 133 -CASSENG is the real-time simulation run-time engine. It is used to make a calculation from the model data file. The simulation can be controlled by using command such as "freeze", "iterate", "run". CASSENG supports Dynamic Data Exchange (DDE), so that Lab VIEW is used to represent the plant's simulated data via its graphical user interface. -LabVIEW is the user interface development environment for the purpose of developing user-friendly graphical user interfaces for simulator applications. Graphical screens with buttons, icon symbols, pop-up dialog, etc. can be created using LabVIEW for Windows. Through either DDE or TCP/IP, user interface screens request data from the simulation running in CASSENG for display and monitoring. SIMULATION RESULTS From the ECCS model, the simulation is run at 100% full power in steady state condition. Fuel sheath temperature in channel #1,2,3,4 is 310.64, 310.68, 310.74, 310.68 c , respectively. The pressure at ROH1 and ROH2 is about 10000 kPa. These fuel sheath temperature and ROH pressure are approximately the same as the values from existing CANDU-9 simulator. Then the malfunction button is push to insert 100% pipe break malfunction. The major event sequence for this break is shown in Table 1. Table 1 Event sequence for 100% break near RIH1 Event Time (second) Break initiation 0.0 Reactor trip 1.0 LOCA signal 15.0 Open gas isolation valves and RWT valves 28.0 Rupture disc RD1 bursts 33.0 Rupture disc RD2 bursts 33.0 Rupture disc RD3 bursts 33.0 Rupture disc RD4 bursts 33.0 Rupture disc RD5 bursts 33.0 Rupture disc RD6 bursts 33.0 Start recovery pumps 48.0 134 Table 1 Event sequence for 100% break near RIH1 (continue) Open sump isolation valves 68.0 Close all gas isolation valves 115.0 Open low pressure isolation valves 126.0 The reactor will be shut down 1.0 seconds after the break initiation. The reactivity change is emulated , rising up from +1 mk to +4 mk in 1 second after the break, leading to reactor trip due to high neutron log-rate. From existing CANDU-9 simulator, -84 mk reactivity is inserted to trip the reactor in less than 2 seconds. Simultaneously after the break, fuel sheath temperature increases significantly because of increasing reactivity which increases reactor power. In addition, loss of coolant during the break reduces the capacity to remove heat from the reactor core. More importantly, heat transfer coefficient decreases sharply due to the effect of the higher coolant temperature. As soon as the break occurs, there is the reverse flow from ROH2 back to the broken fuel channel. Due to the loss of the coolant through the break, the flowrate in the fuel channels decreases until it is less than 100 kg/sec, which takes about 14 seconds after the break, that will result in decreasing the heat transfer coefficient from 36.362 to 0.5 kJ/sec- c in 10 seconds. The fuel sheath temperature will rise up from approximately 310 c to 937 c in channel #1, the broken channel. Figure 4 show fuel sheath temperature in channel #1-4. CH1 CH2 CH3 CH4 200.0- Fuel sheath temp, in channel^ Figure 4 Fuel sheath temperature in channel#l-4 135 As soon as the break occurs, the pressure at ROHl and ROH2 decreases very rapidly because of depressurization in the PHT system from 10000 kPa to atmospheric pressure in less than 10 seconds. In reality, the pressure should drop very rapidly when the break occurs to the highest local fluid saturation pressure 4. Lower than alarm set-point at 7000 kPa, this pressure will initiate alarm signal showing ROH2 LOW PRESSURE alarm following by ROHl LOW PRESSURE alarm on alarm bar in 2 and 6 seconds, respectively. Figure 5 shows pressure decreasing in ROHl and ROH2. R0H1 Pressure 10000.0-1 R0H2 Pressure I 8000.0- 6000.0- 4000.0- 2000.0- 0.0- Figure 5 ROHl and ROH2 pressure after 100% pipe break Receiving two alarm signals, LOCA signal is initiated showing LOCA alarm on alarm bar in 15.0 seconds after the break which is quick enough to send the signal to open gas isolation valves and reserved water tank (RWT) valves. After the break 28.0 seconds , all RWT valves and gas isolation valves will be open. The flowrate of the water from reserved water tank to reactor building via RWT valves is about 3820 kg/sec. After gas isolation valves are open, the pressure in water tanks increases from 200 kPa to 6.7 MPa due to gas leaving from gas tanks. The pressure upstream of rupture disks reaches 2000 kPa. Rupture disk (RD) 1, 2, 3, 4, 5, 6 burst in 33.0 seconds after the different pressure between upstream and downstream is greater than 300 kPa. The water is injected into PHT system. According to the water injected to PHT system, PHT pressure increases to 6000 kPa and fuel sheath temperature will drop rapidly from 937 c to about 450 c and slowly decrease to 236 c. After the break 48.0 seconds, recovery pumps PI and P2 will be started in circulation mode waiting for the 136 signal to open sump isolation valves. The signal is generated to open sump isolation valves after the break 68.0 seconds. The pumps will operate in that mode until the water level in one of four water tanks reaches the level at 10.0 m in 115.0 seconds after the break and then gas isolation valves are close. Consequently, the pressure in PHT will decrease to about 1800 kPa. The signal to open low pressure isolation valves is generated 126 seconds after the break. Flowrate to all headers is about 150 kg/sec. In recovery phase, according to reducing in flowrate to headers, the fuel sheath temperature will continue to go up and remain constant at 350 °c. CONCLUSION This ECCS simulation is a stand alone simulation which can only implement for analyzing the large break near RIH1 according to the method used to created the network modeling. In this model, it is found that the calculation results from network solver, such as pressure and flowrate in ECCS are consistent with the values from design data of initial condition in normal operation and for recirculation mode in recovery phase. The deviation of these result values is less than 10% from design data. Moreover, for monitoring and operating the simulation, the interface of the calculation engine and user interface screens performs very well in real time mode. ACKNOWLEDGEMENT The author wishes to acknowledge financial support during this project from Thai-Canadian HRD project. REFERENCES l.M.Y Ohn, J.H. Choi, S.H. Jung, M.R. Lin and R. Holmes. CANDU6 ECC line break analysis: The Fifth International Topical Meeting on Nuclear Thermal Hydraulics. Operations and Safety. China, 1997. 2.Atomic Energy of Canada Limited. CANDU Emergency Core Cooling System Flowsheet 69- 34320-001-01-FS-O and 69-34320-001-02-FS-O. Canada. 3.K.Y. Lam and M.J. MacBeth. Multi-purpose use of the advanced CANDU compact simulator: The Fifth International Topical Meeting on Nuclear Thermal Hydraulics. Operations and Safety. China, 1997. 4.0wen C. Jones, Jr. Nuclear reactor safety heat transfer. Hemisphere Publishing Corporation, 1981. TH9900015 TH9900015 137 PP/HDPE vmaiu s-nuuerc uas vawu fiaisnvienfrmpn 10520 f 3269982-4 Ivntm 3269981 10, 20 uns 30 kGy 30PP:70HDPE (Twin screw extruder) ^fnilJt11101JH0-3m?WflfJJminiJ 50 30 kGy HDPE HDPE 30 kGy wo HDPE Radiation Improved Mechanical and Thermal Property of PP/HDPE Malinee Chaisupakitsin, Chatwali Thammit and Chaivat Techakiatkul Department of Chemistry, Faculty of Science, King Mongkut's Institute of Technology Lardkrabang, Tel. 3269982-4 FAX : 3269981 ABSTRACT The mechanical properties, thermal properties and gel contents of PP-irradiated HDPE blends were studied. HDPE was gamma irradiated in the dose range of 10-30 kGy. The ratios of polymer blends of 30PP:70HDPE was mixed by a twin screw extruder at speed of 50 rpm. Irradiated HDPE with 30 kGy showed the highest gel contents. The blends ratio of 30PP:70HDPE (30 kGy) shows better heat resistance than the blends with non-irradiated HDPE. With increasing the radiation doses, the mechanical properties of the blends were improved. 138 i/yivn iVmiJ0' (Polymer blends) cK-31S;UllV<0Sm0?NPfJJ1OS;illvifni'UTll0^ (2 3) os iation) ' EJ <4) sTi'ii^ PP:HDPE iilu 30:70 l. 1. 2. voB'mo'Ma'u (PP) 3. Iflf 9-wmj'Ha0Ul'Hai1SUUllmiUUinaa'}M'U0Ufi (Twin screw extruder) 4. 5. 6. 7. lfl1O^0P110'UimSilflf 0-a0?imiJ?'3U'n4llJJimiJ (Compression Molding) 139 8. A IR, DSC, TGA 9. ififg-jvifipf Xim-mBUm (Deflection Temperature Under Load, DTUL) 2. HDPE 160, no ims 180 ^ 10 kGy, 20 kGy ims 30 kGy 3. HDPE fTu PP Twin screw extruder 160, no, 180 tms 180 PP30 ffTU HDPE 7Ofni4 HDPE 70VI1M HDPE 70ttlU HDPE 70ttTU (OkGy) (10 kGy) (20 kGy) (30 kGy) 140 Infrared Spectroscopy (IR) IR HDPE 10 kGy, 20 kGy ims "* (5) 30 kGy BS; I 30PP:70HDPE IR Vt* HDPE (% Gel) ¥ HDPE HDPE PP Jf 141 PP, HDPE ims PP:HDPE %Gel ttfmwnilJ'UeNijff (kGy) 0 10 20 30 PP - - - - HDPE - 16 16 24 30PP:70HDPE - 5 14 14 1 3.1fman%n$OJ'HfJJJm? Ha9iJmai (TJ (Tc) fllEltiifrijfl Differential Scanning Calorimetry (DSC) DSC nun HDPE Tm mnnHDPE YI T IJO-J HDPE • «/ IIQ^HDPE vnm TC "ue-3 HDPE 30PP:70HDPE m Tm "UQ^J PP c liliSu 169 HDPE HDPE PP HDPE HDPE lu PP ueatu PP HDPE HDPE Tc iluviuin HDPE PP (Co-crystallisation) (ilJ 2a) ef^^4V^OalU0?W?TJJ^S HDPE PP PP QiJ 2b, 2c ims 2d) HDPE iyiilM ppiiitninioinpiHannunu HDPE 142 (Tj iias (Tc) Tm(°C ) vifnuJimj?-^ (kGy) TC(°C) vifnui (kGy) 0 10 20 30 0 10 20 30 pp 175 - - - 122 - - - HDPE 142 152 153 148 120 119 118 118 30PP* 169 169 169 170 121 126 125 126 70HDPE* 141 147 144 142 121 119 120 120 r HDPE*lunofuuoiwtTJJ 3OPP:7OHDPE 121.0 PPIHDPE 0 kGy 119.4 126.1 120.1 PPIHDPE 10 kGy o 125.0 PPIHDPE 20 kGy 119.9 126.2 PPIHDPE 80 kGy Temperature (°C) DSC B 30PP:70HDPE 8.2 miflntnf1T5nwinv»P10fniW10W(?lil!Ji11flSn Thermogravimetric Analysis (TGA) i TGA nini HDPE os;vivifmu!'oi4l^-3nin PP uas^infu HDPE vmio 10 nas 20 kGy tisviufmul'a'uipi'^^uwijjaifi'iiiwamtiijn'ii HDPE \,vm\ 30 kGy viijfmjjl'aui^iwia^ eiwmwnninpi Chain scission C l HDPE viufmjjfoui^Qoa^ nwedi^linwujfi'-jff^n'ii HDPE 143 120| Pure PP (289*C) Pure HDPE 0 kGy (436*C) Pure HDPE 10 kGy (461*C) Pure HDPE 20 kGy (466*C) Pure HDPE 30 kGy (4S8*C) Temperature 100 200 300 400 500 600 700 ("O TGA 1)0-) PP lias HDPE 30PP:70HDPE tnnws'UQ'j TGA YHJII mawmj PP a-alu HDPE HDPE ha-3 OHfl 436 °C llJllIu 357 °C) lUQ^'Oin PP^Se^iilJ HDPE ff-JNaliiiliJjifufjnjjiilwwanlij HDPE HDPE HDPE HDPE PKHDPE 0 kGy (367*C) PKHDPE 10 kGy (394*C) PPIHDPE 20 kGy (440*C) PPJBDPE 30 kGy (446*C) Temperature 100 200 300 400 500 600 700 (*C) TGA 30PP:70HDPE 144 3.3 Deflection Temperature Under Load(DTUL) DTUL wim PP yivifl99,tuwn{mVhl>iu9Ufli1&T-an'i'iHDPE PP 3 ni (Tg) fj-anri tfimuwBiujjeiVmu 30PP:70HDPE DTUL nun HDPE munii«ien^nfnm^9wafls:THVh DTUL ?Nfm HDPE HDPE vimums'vnen^'vi'ilMfh DTUL 3 uawwafmflntnena DTUL DTUL (°C) ^fniJJl'UJJl-3^ (kGy) 0 10 20 30 pp 88 - - - HDPE 59 - - - 3OPP:7OHDPE 64 70 65 67 4. 4.1 (Impact strength) HDPE PP HDPE HDPE U9-3 HDPE 1w PP fllWYVUmilPimiiWiZUWf) (kJ/m ) ^fniUlW^^ (kGy) 0 10 20 30 pp 1.7 - - - HDPE 17 - - - 30PP:70HDPE 4 4 3 3 145 4.2 mi11flfr01JflllJJ11l4Ti™fl0H1^Al£Hfni9^ Tensile Testing Machine PP flSJJfn Tensile strength at yield, Stress at break UHS Modulus aufni HDPE fhufmooasmittaijo-a PP ssphrm HDPE thmuwomuoiwmj 3OPP:7OHDPE snflWflfmYlflflfBlJyiimfh Tensile strength at yield lias Stress at break 1)0-3 • i if phgdi-avifj HDPE Hnufnifliejf^^flsmu^uwiJjfmjJi'uiJ'ue-if^ Il4 HDPE 8WH00 Tensile strength at yield lias Stress at break cispia-3iw0fnniJi'uiJsuo-3f^m'W}j^'u tTivifii Modulus Stress U?ifiil'8£ias;fni«Pl^ll?ias;fmJJl 30PP:70HDPE Tensile Stress at Break Elongation Modulus (kGy) Strength at (N/mm2 ) at Break(%) (N/mm2) Yield( N/mm2) pp 32 30 14 687 HDPE 22 3 64 110 30PP.70HDPE 20 5 9 509 10 16 10 5 415 20 17 17 4 474 30 20 20 5 543 v HDPE nu HDPE IR fls a/ V V (Tj j PT^ 146 thmiJfllJijiinhrmmithmiJfllJijiinhrmmiffh Tensile strength at yield, Stress at break VIHDPE Iiii&hijmittiul^tm^n'heheu'uvi HDPE wiufmtiiofm 10 kGy ue-ai^ffmij'uuiilu 20 ut\z 30 kGy HTu HDPE HDPE Hm8iwituis;'H'3i-33OPP:7OHDPE fjtumf?it4 ai lenan-5 1. Chanda, M. and Roy, S.K., Plastic Technology Handbook, Second edition, New York, Mancel Dekker, Inc. 1993, 561-564, 823. 2. Richardson, T.L., Industrial Plastics : Theory and Application, Second edition. New York, Delmar Publishers, Inc. 1989, 407-415, 521. 3. Reichmanis, E., Frank, C.W. and O'Donnell, J.H., Irradiation of Polymeric Materials, Second edition, Washington, American Chemical Society, 1993, 1-8. 4. nqyftn fltnmi. 2541. sYiSnn'uo-JiniijmwftJJim^SS 5. niiM au?^vi5 ims QJJI 2535 ViWI 108-192. TH9900016 TH9900016 147 150 nTaTififl ihmiJifrH Kiltyijqa* uasftaii»uaftaii»m lo fltuciimrn Idyll tTfinjumfiTviTaoiiifjj^na intnniflfnflyntm q.iSculwiJ 50300 # rnntfui«MiasYTwuiiYiinfntr«rcuasiyif)Iulao uTnintnatiiStMiMU 50200 nifnvirlnW musiTitnffiflw? UTniKitnflMWjlid 50200 150 nlaliaw 350 8 1^niwufifjQi'Hfj2mjJD0-au«in«lfl3Jin'U 65 A 150 kV Isolation Transformer for a Neutron Generator Chanchai Dechthummarong Pijit Pr a turn tip Chome Thongleurm Pathom Vichaimongkol* Rachain Charoennugul* and Thiraphat Vilaithong* + Department of Electrical Power, Rajamangala Institute of Technology, Chiang Mai 50300 # Institute for Science and Technology Research and Development, Chiang Mai University, Chiang Mai * Fast Neutron Research Facility Department of Physics, Faculty of Science, Chiang Mai University, Chiang Mai ABSTRACT The work aims at the design and construction of a 150 kV isolation transformer for a neutron generator. The transformer windings are designed to use cylindrical layers with circular enamel copper wires. The insulation of the dry type transformer uses the epoxy resin for encapsulated winding. This insulation is non-flammable under temperature 350°C and the breakdown voltage is 10-18 kV/mm. This insulation is suitable for insulating high voltage. The design of provides the temperature rise of winding not exceeding 65°C for protection of the cracking of epoxy resin due to the expansion of winding. 148 UT1W1 tninioms 3 MeV 2 2 3 ,H+ ,H 2 He + n 14 MeV 2 it 100-150 kv ii-aTmforn0i0'u( 1H -ins) 0141VI -W/7//////7/////777777, 220V 50 Hz 150 kev 149 mmonisnuniiiiJi qsri uw fjvtsntmifmfoflnu iw trssin 220Vac 1M as fliUfJJJ ^ 150 Araldite F lias; Hardener HY905 U04 Ciba Speciality Chemicals (Thailand) Ltd. 150-200 8^ff1le)fai5t)i1 20 SWG, 18 SWG uas; 16 SWG 150 l m\. l JJJJ. jms; 1.5 uu. 10 150 (0 20 mbar Araldite F lias Hardener IKIS mowu i50°c soTm (U) flw 150 nla ii5-i«ijn«fr0ij 5-10 no (i) ^ nomi Hftfl 1 110/130/240 V 2 uf^«wrj«8fj2 130 V 3 R-31UQ 50 Hz 4 1 - 5 fnsumJjjjfiS 2.73/2.30/1.36 A 6 2.30 A 7 ma-ai'Htli 300 VA 8 fmugsymon)fus1iJ2iMa« 6 W 9 fmjjgqjmouQisSI'Hafl 15 W 10 ui-3« 00 45 JJJJ. - ^=63.6 UN. T 45 111J. fi 3 B-H Curve (Lamination Factor) f115 (Bmax) 0^ 1.1 wb/m2 (iii) FxlO8 N=- novo , Npl = 220 58U .) # 20 SWG < IV Nsec = 0 V C 1 !130V # 26 SWG p2 = 260?Ou)")||| g #18 SWG 130VO 152 (iv) mmi\f)nfmumniiuuvmf)i3ZiimzQ$\\i'sii 1-3 A/mm2 [6] 2.07 uas 1.971 A/mm2 20-25 mm luufiasaiu mifho 1.109 v y 1 A/mm2 ^1414 aQ«H j;S'WW^'Hyi«fll11inil 0.656 mm2 was 1.167 mm2 2.674 mm2 (v) (i) (ii) v) (vi no 150 10 kv/mm [7] 153 aoamstisw 0.8-0.9 W/m-°K [7] ma 65 iv) vii) 11TUO (i) H^IQ ni1 90.00 187.00 24.00 452.66 17.00 10.00 44.50 100.00 44.50 100.00 190.00 jiJfl 5 nTM««D0^iHy0uiJa-iimi;is;tispii-3ir| 154 (i 6 (n) 6 (u) om 44.50 o c /I ! i ! I 100.00 190.00 ! j 44.50 O i O 100.00 190.00 65 uu. 10 JJU. HM mow (in) 15 ?0JiiT (iv) 155 (v Aradife F ilt\t Hardener HY 905 Iu0fl51?bu 1:1 80°c ©on 90°c 5-20 mbar [7] 90°c 0-3 15O°C 5-10 m 156 (0 mi (ii) 8 uns; 9 siiKi 8 im«^o-3fniug«ymoino1wMW0iiiJn4 8 n) 240 « Sfhmi nu 2.12 w ^ 8 v) iilufm¥ifl?r9iiDQis21wafl m 1.25 A i 2.44 w ebu|iJti 9 u^ai'Hfj5i'HU 9 (n) ims( •Hffamffa 300 VA irlfY 1 50 Hz imm40 nissiifrSwjjw 1.25 A 2.31 A LV-E(MD) HV-E(MD) LV-HV(MQ) fmuflfmYiiuno-a'BUQUvtiJOUiJfu 10000 100000 100000 liMiin4Q4n»ufmi4 (kv) 150 60 fmrfiwtu ©PintY'J XI HI 14 Q147011 LV HV LV HV LV HV 220V 118.5V 220V 120 V - 1.25% fmumuYiTmjowflaQfmo.aiwfjS 75 °c 3.36 1.56 3.65 1.44 8.63% -8.33% U7-aflU01i'WU«lll4cB^0-lMW0lllJa-3 5.41% 9.75% 44.51% 10 157 2.5 3 n 2 1.5 t 0.5 0 o o o o o o to o in o m o T- •>- CVi CM CO Voltages(V) o Current(A) n) v) 12 T 10 ^-.. 8 6 4 2 0 2 3 4 5 6 Times(Hinutes) n) jiifi 9 10 158 euMUjniu wii iim 90 °c sizm*\$nt\w\i\n\iinf\ ihsintu l imn • v « fl8 8{j^ 50-60 nlaiQawmiiT'U lJ5S;ni1^tT8^fie m^HtfU Araldite F niJ Hardener HY9O5 \\i m^mu i:i mew erii^ifltno^ljJiie fmSfmim '*iv a tilunni 14 vilu^ m8Mif!iifniu«iWYnwt)8^fla'3«^naii5u«'uSfiiminij 1.422 47.i9°c 150 S 300 lie 159 nntmrnhsnift fjautrifl ewn^Sf uwun UQDOUfJIM qQltjU-3fll1 U?yYl Ciba Specialty Chemical (Thailand) [l] oswwu Qaovi9«j, l, , 2540. [2] 1,2535. [3] , mfnvnfnfmu'WIh , 2528. [4] ^ rlSn« fifusinoiffifTwf, utnintnaoivo^lMii, wui 1-2. [5] A. Stigant, J & P Transformer, 10* Edition, Buttor worth & Co. Pubbishing, 1973. [6] H. Banspash, Transformer Design, Lecture Notes, Thai German Technical Teacher College, Bangkok, I9, ed., 1975. [7] .Instruction Manual, Araldite Casting and Impregnating Resin System, Ciba Specialty Chemical (Thailand) Ltd, June 1980. [8] Catalogue No. exe 320, Nippon Steel Corporation, Tokyo, 1988. 160 3°§ Burnt Qi^fli qpna ljaiQiffiiHs uas erstm? jim^m nifiTin'CbifiatmYifiIuTcie) fiaisnfnn^ufnfrm 2186782 Ivi5?n5 218-6770 V V NT.2612 2 friiiMan eniiuin JU RS-232, IEEE-488, BCD myanaiainaon > 150-9600 Ci 10 1200 1 y 1 Hasfn3iT^ An Interfacing System for Radiation Surveillance Using a Radio Communication Network Thanakorn Arunsiri Suvit Punnachaiya and Attaporn Pattarasumun Department of Nuclear Technology, Faculty of Engineering, Chulalongkorn University Tel. 218-6782. Fax 218-6770 ABSTRACT The development of an interfacing system for environmental radiation surveillance using radio communication network is aimed to improve a way by which environmental radiation measurement is transmitted and reported from the regional area monitoring station network. This also includes an automatic warning of beacon status via the radio link network to the center of environmental radiation control when an abnormal radiation level is detected. The interfacing system was developed by simulating the EGAT radio link network, the NT 2612, and can be separated into two parts. The first part was for a mobile station which can manage the output data from the radiation measurement system in the standard form of RS- 232, IEEE-488, BCD and analog signal. This was accomplished by modulating the signal in selected baud rates ranging from 150 to 9600 bps using an economical radio packet capable of identifying and recalling the station code number. The other part is the linking system between the output data and the microcomputer equipped with a software to manage and evaluate the data from 10 surveillance stations for convenient handing of data output, statistical analysis and transmitting warning signal. Data transmission was tested using a baud rate of 1200 bps and was found to contain no detectable error when digital signal was transmitted while analog signal transmission resulted in deviations of less than i 0.003% The development of this radio link system provides a future trend for the environmental radiation monitoring network for countries with nuclear power plants or neighboring countries needed to continuously monitor for any abnormal radiation level in the environment. In case that the radiation surveillance system detects a high level of radiation, a warning signal will be transmitted and appropriate actions may be immediately exercised to control impacts of radiation on environment and living things according to international guidelines. 162 l. imih ivu y y mitta (incidence) v y y y y ui •wi9iJin-3'3i-3HH y y on ©ag 163 y v 2.1 2.1.1 y v (pager) 164 0 165 2.1.2 *'ci*' ivu HPGe 2 nmj fi. Nuclide Specific Monitor HI911 y y 2.n. y numi'm 1J. Doserate Monitor 2.u. (indoor) 2.f). irn aim" BCD, , RS-232 UIJU radio modem 166 I fl. Nuclide specific monitor II. Outdoor doserate monitor fl. Indoor Doserate Monitor (3) 167 2.2 A « a/ a/ a/ ,=* z1—N lfl5Q^JJO DATA MICROCOMPUTER niJ (packet) ?Qunin'mY RTS "polling" 168 TO RADIO MODtM NT.2612 169 (Mcs-5i) 2. 5i;iJllflJD9Jjafl1f1lfif9>J09W5-3fl'!'fllJ?U1Qi5^^9n^ q Win fm51JU9JJ£MlJlJ RS- y • v i y y y 232 to ic iu9i MAX232 ymtu'miij'ugija fmrumgiJEHiiJiJ BCD y * IEEE-488 Iv IC iUOf 74245 2 Iffi liTHUmfl'UljVlirlg? (Buffer) & y CPU MCS-51 m-Jij'n'ugjyfi (Data Bus) ic iijg? ADC0809 iiTHa4i^tiiJa^ 3. f115if)?)951J-Pf-3 MAX232 Wf)?19H1\4yn-3'H91«1 3 U93 CPU fnf)9?l51D9Jja 1200 bps 4. 8155 5. m5rn5i0m9? LCD 3. MCSSI MAX232 fofmentnsiJijfiJimgijmnflss™ RS-232 i5 (radio modem) *ntJ9Vmfm?Y-mfl]GnfU 1200 bps 1jJ ADC j^ * lJ^ 5 uas 6 170 nlvi 5 |lJfl 6 n. miiit)nnn\j?tfmj A4 A5 171 fl. -a. 4. 4.1 v 12(K) bps 2. DOS V V io tttnw 4. cross talk 172 4.2 l. l 2. Jafi 1200 bps ^OlflSlliljlTtinfniWflSWQ^Iv radio modem 5. Y\ y *H 6. 1. IEEE Transactions on nuclear science, Vol. Ns-35, No.l, february, 1987. 2. Environmental radiation monitering around tokai reprocessing plant. environmental protection section, health and safety division, tokai work, power reactor and nuclear fuel development corporation. 3. Nuclear and radiation protection system, berthold, EG&G. nuclear instruments division. 4. Winch, Robert G. lekcornmunkation transmissiQa.systems. New York: McGraw-Hill, Inc, 1993. EW5 173 wrHtfahipi tpm i\v*v*istiuz nas IAIV newsiu 218-6782 Ivnmi 218-6770 o ^ 20 nTaomnfiioulQa^ nisiitriui^^ii 10 UIT'UHOJJUIJ? 9.71 nlaeiantnieulinw (La x-ray) 2 0-3 50 mi ^ 80 JEOL \U JSM-T220 imsSSlUjnil'UPI^^lOn'K^flWll'lJi'UU ifltlKflfflPnivlvlil^ 20 S'piisjosTii^fnm^lio-aSuwiotJUiifissnfiiiln^vlaiJmoiilaownin^'utnw^ 2 nas; 5 mi 9iijjai^u Wnaitiiamw 60 uivi ffiovlaw Agfa STRUCTURIX D7 rih 2 ivii l^fniunuvpnipimtjunu uois;^fnvi£ii«nia^<«tno 5 V nii 174 TH9900018 TH9900018 Modification of a Cathode Ray Tube for X-ray Microscopy Vimol Supsongsuk. Suvit Punnachaiya and Decho Tong-Aram Department of Nuclear Technology, Faculty of Engineering, Chulalongkorn University Tel. 218-6782 Fax 218-6770 ABSTRACT One of the disadvantages of conventional X-ray radiography is its inability to magnify image; and thus, fine details of millimeter-size specimens may not be resolved. To overcome this disadvantage, a microfocus X-ray source is needed; and at present, it can only be generated by activating atoms of a metal target using electron microbeam from an expensive electron microscope (EM). The technique is known as X-ray microscopy. This research work is aimed to modify the electron gun section of a cathode ray tube as an economical microfocus soft X-ray source in a vacuum chamber. When the electron beam has an energy in a range of 0-20 keV and a current in order of 10 nA. The beam is focused on to a thin film gold target, a La characteristic X- ray with an energy of 9.71 keV is generated. The X-ray projection mechanism can be adjusted to magnify an image by 2-50 times. To benchmark the modified X-ray microscopy system for its spatial resolution and image quality, X-ray micrographs were taken on the 80 \xm of copper wire and small fish (GUPPY- Poecillia reticulata) using the modified electron gun and compared with those taken using an electron source from a conventional EM, JEOL-JSM-T220. Testing conditions of both systems were configured to operate at a 20 kV accelerating voltage and a setting of target to specimen distance and a target to film distance for x2 and x5 of magnification, respectively. The exposure time was set to be 60 min using an X-ray film type Agfa STRUCTURIX D7. The image quality obtained from both systems was found to have comparable degree of sharpness at x2 magnification. While, at x5 magnification shown the unsharpness of X-ray image from the modified system, due to a limitation of spot size of electron beam which is controlled by electrostatic focusing lens. 175 l.umn on'Bviu^ mnmanijin (microfocus x-ray source) ^^ (x-ray microscope)" (cathode ray tube) (soft x-ray uuagB 2.1 ^ 176 (penumbra, [l] x-ray source specimen film- t P nJvn p = w (d,/d.) .(l) p flB w d2 i ^ (scanning electron microscope , SEM) cHfaflfl9-3^fiyi11ft'UQmn?11Q'UHllllY11TUITSclf';2f'U (transmission electron miscroscope , TEM) (M) iiuetjmj [2] 177 M = b/a (2) b = a = [vj. filament electron beam r\\r\ 2 electron microscope ) ma 5-io soft x-ray) 178 i HT. CRT cooling power supply (electron gun) system x-ray vacuum » projector system vacuum chamber -f x-ray image recorder 3 ?TTU m n. I?l5in ( Toshiba ) 114 5UP1(F) 6.3 nisiim 0.6 1.050 lim ti 25 nla 100 lulfiiiiauiiiJi •u. (vacuum chamber) evaporator) UO^UI'yvi Edwards 114 306 30 icBi4WHj(ni tit 36.5 i io"5 viai 90 14TTT diffusion pump ) ^^0^t^^0^tni^l14113JniJ1s;iJlJ'Hfi0mn lU( cooling system ) 18 30 179 fi. ^ "A Simple X-Ray Microscope for SEM" [1] •n-3^m9lll1t(lJm!JlJWf11J0-3ri1idifJniVI^1^lfl1fl1s;i)lJ^!)S;'W9JJUTUU 5 L-x-ray( 9.71 keV [3] -3. ui^vi Fuji in FG Orthochromatic llJ1tJUmtnjniJrlaijdit)fn'W5^m9n(!Kn)a^ Agfa STRUCTURIX D7 "Uliifl 5.9 x 8.2 9nmicB'uwiJjfi? in^piim-3iilv!iivnpi 2.5 x 2.5 -HT 220 filament power supply V cathode grid switching high voltage focus power supply power supply astigmator x-ray projector 2.3 2.3.1 l. 7) 2. JEOL iu JSM-T220 3. 5) 4. ion sputtering nWlATUTU 15 180 5. uwuvl a uri 9 ia Fuji in FG orthochromatic Agfa \U STRUCTURJX D7 V 6. fh 0.08, 0.12, 0.15 2.3.2 2. 3. io 5 YID? 6) 4. n "mafias: fif 3 5. 60-90 6. 7. target lock spring target holder x-ray chamber 181 Jl 3. ion sputtering 15 IIIYl 350 5 ivh 10 n. ,11. ims;|il^ 11 n., m. 5 mi 12 n. tins; u. 182 350 nm Milli Kill 15 I mm n. x 2 , rhfaaViiitntJ x 3 x 5 , rhtUBWutntj x 3 x 6 , ncnditjfnn 60 ^ x 15 , naidifj/nn 60 mvi z\ am 09 wiumumu' si x y Win SV MLURLpLUti 'SIX e X (11IJIIWQN3LU ' g X r)llJM.Lt/nilJlUmU ft, e x fjindwec-uLu' s x u \A\ll \xin 09 'six win 09 kALURiaiuti' 9 x £ X ' S X QLUM,LU(3L(3(ttaLU 'Hi £ X (JLQIVW8MiLU ' Z X RlimitfGlfmC-UlU U C8I 184 4. 4.1 4.1.1 25 niaiifisn lii < 25 niA9mn$ni9'u bfi?)' 20 nA 4.1.2 nT3l?l1tJJJUW'Ull]nrlaUin^Ua-aV19-3^1 (Au) ftlUlt ion sputtering ^Ui^fl'vi 350 V im 15 mA U^illH•U3^^4 3 ink ^9 vJafwiii (formvar) tjJfn (mylar) lt?is;1um (mica) sputtering 4.1.3 350 15 keV Ma x-ray line 1J9-3 20 keV 9.71 keV Bremsstrahlung Bremsstrahlung 4.1.4 Fuji in FG orthochromatic Agfa STRUCTURIX D7 4.1.5 2 mi 4.1.6 v spot a-3 tu 185 %f 4.1.7 4.2 •uoifT'ueim 4.2.1 (electromagnetic 5. ims 6. 1. 15WH C-jfiasif^ ims m niflnifCUmfifo^yOQflWQYIEJIfn^flltlfi^mfl^lfiy tl^ 2Q1JII^ 2(2535):107-137. 2. Emmett F. Kaelble. Hand Book of X-rays. New York: McGraw-Hill Book Company, Inc., 1967. 3. Yada, Keiji, Takahashi, Shoichi. Target Material for Projection X-ray Microscope Obervation of Biological Samples . J.Electron Microscope. 38 (1989). 186 CM mnicu 2/ en in? ISO 11137 IB^ l imufnsi'HiJiinfuf'JiT 25 25 uns; 50 20 - 25 n Modified Lowry 10 - 50 nininiovniii In ifi TH9900019 TH9900019 187 Radiation Sterilization of Natural Rubber Examination Gloves Suwimol Jetawattana , Nuchanat Na-Ranong , Varaporn Kajornchaiyakul I/Biological Science Division, Office of Atomic Energy for Peace Tel. 5795230 ext 581 2./Rubber Research Institute, Department of Agriculture Tel. 5798556,9405712 ABSTRACT The sterilization dose setting by ISO 11137 method 1 was conducted for natural rubber examination gloves provided by a local factory. The suitable sterilization dose for an average product bioburden falls between 20 - 25 kilogray. Maximum dose of 25 or 50 kilogray results in no changes of tensiles and elongation at break. Samples of examination glove were irradiated using various doses between 10-50 kilogray. Analysis of soluble protein content using modified Lowry method was carried out and the results revealed that irradiation did not affect the decrement of soluble protein content in this case. However, thin film samples were prepared in laboratory and treated in the same procedure.The results were also the same. The results did not show any correlation. Two factors are possibly presumed : unconsistency of samples and the irradiation of finished products could not affect those soluble proteins in rubber gloves. 188 13 n.ft. 2537 30 V 1 25 ninmia (kiloGrey, kGy) vtfa (D|o) Hiamii'BK^ef^niT 25 nlfimiU lUJnuSmiH biological indicator (Davis imsflfUS, 1984, Doolan Ucl^FlfUS;, 1985, Darbord Uc\Z Laiziers, 1987, Gazso WflSflfUS:, 1990, Chengyum UtiSfifliS;, 1993) llUlimiHi-J^lJiinfU 25 kGy ^Su 0?1EJ1^a (ISO 11137,1995) AAMI (AAMI,1991) uiK ^S'ua^a'viiili-iiej v v , uifui^oiJusiloiJiijjfiu imsmi'ni sterility test (Sterility Assurance Level, SAL) Y\ 10"21 10" lifU 106 'H3JlfJ^l9fllcT^i)5;^lJNS^JT'flJcVl^i3JlJcia^d0iji'WEJ^ 1 Iviai^?^ VtiflS i (Turjanmaa lia^fltus;, 1988, Czuppon,1993) imslumilJiSW International Latex Conference: Sensitivity to latex in medical devices lull 1992 iiu imwifn vlunnwa pJi-smir ttni^oimm \nfifmflnm Kume UHS Matsuda (1995) t^ antigenicity 189 *iwa^fifucvi 1. pmrniCflfaminUin Cobalt-60 (Gammacell 220) BfinmillHi^n (dose rate) 14.22 lHuifln^fhej Radiochromic film FWT-60-00 91l4f)1flllJJ SHIMADZU uv-3ioip fWi^ay 605 nm. 2. f!-jfiafJ1-3ffTHfllfni?in\)'iifl (rubber examination gloves) J inimi9fhwmi4 4 fi?-j fiT^as 3 line Iflfjimieias; line line a^ 5 na'0^ q 100 5u 3. 0TH11iat)^lf9?S'U'ni£J (0.1 % peptone water, plate count agar, tryptic soy broth) 4. in?flS;aifJ^14fllifniYlPl?T91jllJiWV4 (0.15 % w/v Sodium deoxycholate, 35 % w/v Trichloroacetic acid, 1.6 %w/v Phosphotungstic acid, reagent A:Alkaline copper citrate solution, reagent B: Folin-Ciocalteau reagent) 5. mfawflflaufn'iJjfhimi'WweM'u (LLOYD LRSK) 1.1 YlfltT91Jfni3JPl'TUtl1-3^ (tensile) (elongation at break) line as; 18 5i4 • 25 uas 50 dose control 6 190 [ .'i '-77 (1) dumpbell '0114114 3 20 +/- o.i UJJ. 24 (2) 500 (3) 1.1.2 (l) (2) 70+/- 2 °c nin 166 /- 2 fnujtlfiifiaui?) (fsoat) riBvimiiJui^ Iduatinii 21 liJuaEJflTI 700 liruatifni 16 Ijiijaonii 500 , FOI) pair-t test 1.2 line c\t 60 514 i 25 lias; 50 1fl£Jll?ins; dose V 20 U control 20 ? (l) IOOO (2) 2 U-\Y\ 191 2. iso 11137 imi4fmKiH3Jiaji^ 25 nimnstrvhlil (iso,i995) Dose setting method 1 : stage l menis^ufni •uiui^inBtilu l ) stage 2 fl11\)'H1lliinflU'traiJ hi pi4YiiaYHWifl?n standard plate count) stage 3 'U1fl'liaao stage 4 KfhOEtHQfl 100 SuDifi line polyethylene ^lla0flll0Ui1llfJ1£)74^«nJJ verification dose ^fiTHVI*! UPIT111 sterility test fhfJ soybean casein digest broth iJlJ^ 30 °C l9\4nm 14 1114 lJ?JJ1fU f^S'Mifli'lJi)?^i)S;Pia-3afi1l4(K1-3 verification dose +/- 10 % ims&nSphodniM H?i positive Imnii 2 tw%tifim\M?\f\T)\h sterility test Ifl stage 5 m0f1lJ7U1fl47-3^^mjJlStYJJffTH1Um7lJ?i0fllV0pniJNam7Ylfl?f0lJ sterility test •H1f1fniVlfltt01lfnjJ method 1 1m2l4iiJ(?n3J£lianTHV4fl method 2 (ISO11137,1995) 3. ^fiyiiJiU1fwllll^1l4 PISf1Q42;, 2540) 3.1 vJIEJI^^^iefJi^ti^^QfJI^^ 10, 15, 20, 25 , 30, 35, 40, 45 H(\Z 50 3.2 flnfuiliflutniJYifisfnfJinlflf'ntiinna'u limum 20 ml. 7x7 iwameii MiTnilisinflj 1.5 -1.8 niw iilunm 3 37 +/- 2 °C l^JEJIPlitJWaVlfin 30 VITVl 3.3 ili^a^mcn^i^iiiJiiw^fmiJi^ 3000 g, 15 i4ifi mai 1 V 3.4 141 solution itTJJll^UfiifimaPlfl^^fia'uilJl^'U^'U 0.4 ml. nJB^ 0.15 % w/v Sodium deoxycholate (DOC) 0.4 ml. nja^ 35 % w/v Trichloroacetic acid (TCA) 0.6 ml. IJa^ 1.6 %w/v Phosphotungstic acic (PTA) 3.4 14i1llill4^fniJJlK 6000 g , 30 192 3.5 c\ZQ\~\V?\Zf)miYl\f\f\''W0.2M'NaOH lml 3.6 lflimi5fJ93Jfl reagent A 0.3 ml. b Alkaline copper citrate solution reagent B 0.1 ml. Folin-Ciocalteau reagent 15 "unfi 3.7 r\ 750 nm 3.'8 , Fm) 3.9 mm\l standard curve 1fi,Fluka) 1 mg/ml llPl 5, 10, 20, 40, 80, 120, 160 line l-i, 1-2) aei n^ 1-3) line wini ISO 11137 iffi 1 sterilization dose ^lWJJlS;?r SJJini 22-25 193 3. Modified Lowry V line 128.27 - 1294.32 ^ig/g of glove 50 nlninio 25 50 mimon 25 ims 50 2 3 io M?0 io iso 11137 ilvi 1 fls (D10) iso 11137 line l*UJ Vff 0 processing v v i3!/u4f0W 194 Gammaceil-220 2537 . 'ih^niffnis'nii^tmntufT'ufliJij'vi 13 (y\.fi. 2537) 1 mw ill aauwiffy 58 -3 Y\ 9 SUTlfUJ 2537. 2. uinng fu 121104, navm leiunfminij uasnnfiifu •u'Dii^onn. 2540. 2540. . mivwuiwmvri 3817500013 3. Anon. 1991. Process Control Guideline for Gamma Radiation Sterilization of Medical Devices. Associatetion for the Advancement of Medical Instrumentation. (ANSI/AAMI ST32-1991) Arlington, VA. 4. Chengyum, Q., Qijian, W., Guangcun, M., Binsong, C. and Yunsheng, Z. 1993. Study on commercial radiation sterilization of PVC infusion sets. Radiat. Phy. Chem 42(4-6):591-593. 5. Czuppon, A. B., Chen, Z., Rennert, S.,Engelke, T., Meyer, H. E., Heber, M. and Baur, X. 1993. The rubber elongation factor of ruber trees (Hevea brasiliensis) is the major allergen in latex. J. Allergy Clin. Immunol._92:690. 6. Darbord, J. D. and Laizier, J. 1987. A theoretical basis for choosing the dose in radiation sterilization of medical suppliers. Int. J. Pharmaceutics. 37:1-10 7. Davis, K. W., Strawderman, W. E. and Whitby, J. L. 1984. The rationale and a computer evaluation of a gamma sterilization dose determination method for medical devices using substerilization incremental dose sterility test protocol. J. Appl. Bacteriology. 57:31-50 8. Doolan, P. T., Dwyer, J, Dwyer, D. M., Fitch, F. R. ,Halls, N. A. and Tallentire, A. 1985. Towards microbiological quality asurance in radiation sterilization processing: the limiting case model applied to a microbial population having a distribution of radiation response. J. Appl. Bacteriology. 59:189-194. 195 9. Gazso, L. G., Dam, A., Molnar, A and Daroczy, E. 1990. Determination of radiation sterilization dose of disposable needles based on D10 values and AAMI recommendation. Radiat. Phy. Chem. 35(l-3):404-407. 10. ISO (International Standard Organization) 1995. Sterilization of health care products- Requirements for validation and routine control-radiation sterilization. ISO international standard number 11137. 11. Kume, T. and Matsuda, T. 1995. Changes in structural and antigenic properties of protein by radiation. Radiat. Phy. Chem. 46(2):225-231. 12. Program and Proceedings International latex conference: sensitivity to latex in medical devices. November 5-7,1992 Baltimore, Maryland. 13. Turjanmaa, K., Laurila, K., Makinen-Kiljunen, S. and Reunala, T. 1988. Rubber contact urticaria: Allergenic properties of 19 brands of latex gloves. Contact Dermatitis. 19:362-367. 196 Table 1 Mean values of maximum stress and elongation at break in each line before and after irradiation at various doses* 1-1 : Maximun stress(Megapascal) sampling before aging after aging Control 25 kGy 50 kGy Control 25 kGy 50 kGy 22.98 22,65 23.60 23.38 21.46 20.32 1 28.41 27,10 26.95 23.77 26.53 25.21 25.88 25.83 25.71 23.75 23.09 25.46 26,76 25.38 25.42 28.04 28.23 27.07 7 24.99 24.84 24.27 23.11 22.40 24.48 25.13 27.41 27.92 26.38 27.56 25.58 24.80 25.57 23.90 23.62 22.93 24.40 3 26.81 25.58 26.66 24.46 22.38 19.73 23.82 24.77 21.85 23.39 20.98 23.43 21.99 20.33 20.92 22.81 24.93 23.83 4 22.10 21.13 21.68 23.56 23.33 22.93 22.10 25.29 24.21 24.75 24.00 25.84 average 24.64 24.66 24.42 24.25 23.98 24.02 1-2 : Strain at maximum load (%) sampling before aging after aging Control 25 kGy 50 kGy Control 25 kGy 50 kGy 1450 1484 1508 1420 1421 1342 1 1531 1483 1480 1378 1364 1425 1429 1420 1498 1439 1381 1424 1533 1422 1467 1348 1435 1409 7 1499 1451 1446 1378 1319 1361 1486 1466 1505 1434 1440 1385 1584 1592 1609 1532 1600 1604 3 1646 1650 1672 1581 1578 1528 1540 1571 1583 1516 1516 1545 1562 1481 1514 1499 1491 1474 4 1589 1451 1537 1561 1492 1464 1643 1580 1528 1563 1564 1508 average 1541 1504 1528 1470 1466 1455 *Each values averages from 20 test pieces 197 Table 1 (Continued) 1-3 :Effect of aging condition on test parameters; Test parameters Dose condition of aging' Test values" (kGy) before after Tensile 0 24.64 24.25 0.640 25 24.66 23.98 0.880 50 24.42 24.02 0.505 Elongation at break 0 1541 1470 4.289 25 1504 1466 2.433 50 1528 1455 5.180 Means from 12 lines replicated. 2 paired -t test; df = 11 , Critical value (FOOI) = 2.718 Table 2 Determination of sterilization dose (ISO 11137 method 1) Sample set Average number of microorganisms/item Sterilization dose (kGy) I 952.73 24.9 II 1232.59 25.3 II 5213.16 22.9* IV 860.00 24.7 *The actual dose was not within the specific dose range and the sterility test were not acceptable; therefore an alternative method (method 2) was used. 198 Table 3 Means of water soluble proteins in irradiated samples at various doses Dose (kGy) Means (ng/g of glove)* 0 (control) 726.19 10 813.07 15 774.73 20 767.90 25 858.07 30 762.16 35 792.82 40 852.70 45 781.97 50 751.17 "Values are average from 12 lines (C) 201 10900 Tni. 579-5230 WO 511 TmtTn 561-3013 (T.F.) 137 ims:a'm9ui'&mj-8i'& 5 rias acrocephalus) llf1s;ilai^fimflf(Clarias garispinus african sharptooth) f 1000 H«? ^S§i§ou-137 ut\z ?im®ummi 42 TU ^1%4QfUf)1 T.F. 1?lt)Hl!lJllfl1f10-3 single compartment exponential uptake model 1&h T.F. "UO^WOU-n? i!J1s;£TY150'UI§t)3J-85 limTUrdta mz%n if S 3.2, 2.6, 1.6 lias 1.5 n«si7.nn.: uns o.n, 4 , 2 ims 17 41 (ins 4 uv\ 202 TH9900020 TH9900020 137 85 Transfer Factors of Cs and Sr by Freshwater Fish in Tropical Environment Fookiat Sinakhom, Pattra Supaokit, Suntaree Kaewpaluek, Nanthavan Chantaraprachoom, Monta Punnachaiya and Nikom Prasertchiewchan Waste Management Division, Office of Atomic Energy for Peace. Chatuchak. Bangkok 10900 Tel. 579-5230 ext. 511 Fax. 561-5013 ABSTRACT The experiment was set up to determine the radionuclide transfer factors (T.F.) of Cs and Sr by tropical freshwater fish. Mixed breeding catfish between Thai catfish (Clarias acrocephalus) and African catfish (Clarias garispinus African sharptooth) were 137 85 exposed to Cs and Sr in two 1000-L tanks for 42 days during uptake phase. The calculated T.F. at equilibrium, in flesh, bone, skin plus fin and head were 3.2,2.6, 1.6 -1 137 -1 90 and 1.5 L.kg for Cs and 0.1 , 4 , 1 and 17 L.kg for Sr , respectively. These results revealed a much lower values than reported elsewhere for temperate environment, however were in accordance with the tropical values as observed by others. The biological half-lives of Cs and Sr in flesh part were 41 and 4 days respectively. It is then imperative that suitable T.F. values are employed in the models to predict the transport of radionuclides within the particular ecosystem and the potential dose to man. Thus the relationship between routine release of radionuclides and resulting dose to man can be established and corresponding release limits stipulated for that particular nuclear site. 203 Mf ennui M?9 (IAEA) uasfifusnnmSnisilB^nu^fmtJtnnftfbsTn^ita^'Mfr (ICRP) (pathway) fqj m f~fi\mt\f\~fi\mt\X\~\'HmSiwhtffl'\%?i$fl nig radionuclide transfer factor (T.F.) R9 ff T.F. M14111414 tT13J1It1^lflS;m0n1l'imi4ni1imi1S;T1lfl'H1s;'M14tM (site specific analysis)1m'U0-at)in5 [l] umfivnufh T.F. 1i4!n)«ienmfr'f©i4S'-3S95iTi4iJ?jjntu'n€ifT« 3^nini'W9lMi^i'vi5iu imj;m1flo-j'wqfln?5uniiifia9i4^ (kinetic behavior) U93fmf3iT na1nn)9-3ni5JTS;?n! Iins;ni5fl-39{j (mechanism of uptake and retention) T.F. v t ijm0 itical pathway) J50-3 " Transfer of radionuclide from air , soil and fresh water to the food chain of man in tropical and sub-tropical environment" IAEA 204 (Clarias macrocephalus) clf-3l^lJin African sharptooth) 25-30 tu. unsiiiTnTn 160-270 niu 1000 Hwi ^SiSniJ^siliuii^©^ 500 m? i^inntn 30 0.3 30 iti •wuQi0«7im??0« 2 vita n© SiStijj-137 ims Amersham ^0 2 MwSfil neutron flux minu3X10 cm .sec 85 -85 205 1000 s 500 30 in 200 ioo nfu (steady state) uptake phase Knill 42 114 fm3JTf V V • •u IK 14 n il a lei9 \1 TH M -3 H« 5 42 QIJ 100 au.im. 0.45 loo au.ifij. it tfiume 450 °c l nfu 8092 0.662 kev lYhfUJ 0.0007 I 0.514 kev m'nnii o.ooio 0.45 1ufll9^ U^TVIiIfltlll Direct Calibration H Calcium electrode rnedel 93-20 imt potassium electrode model 93-19 1193 Orion lhs? 206 ©-0 dissolved oxygen (D.O.)I^tlH portable Aquamerk kid fmiflfhpH im^pH electrode U0-3 Orion ibi Ion-Selective Electrode #ltllflf9-3 pH /ISE Orion model 720 A ibsmmttnpiufm fmiSfm^K Total hardness \ is; (specific activity) 1J93 WHCJJJ-137 ims ftvi?9ui5ti}j-85 luiJainunai tiil^injjiinfnflfism iJfwitUi^ft fll nfliWl \$\ single compartment first-order kinetic process At equibrium, q( t) = (q)e<,(l~e ) f q(t) = ab(l-e"ab(l-eXX'') (1) t = ntn (ivi) q(t) = vife q(eq) = •w PI a 9-3 a = b = (steady state) a/ "I A. = rate coeffcient (114 ) Computerized curve- fitting U0-3 The stastistical Package Sigmastat ( Jandel Scientific, 1994) qf-Jlflnilm? non- linear regression iterative, least square method iPltl The Marquardt-levenberg algorithm.[2] curve- fitting 2 compartment model using transformed data f\l\i q(t) = cd-e^") +d(l-e"l2t) ma c + d = (qwimfn transfrom vati m log) 207 (1) 1#TfltrYh back-transform fil c + d (c+d) .". a = (10 -l)/b = radionuclide transfer factor T.F. lutrumi (i) mefliuiniinfiTHinijiwe? X T1/2 1/2 In 2 1/2 uptake phase Table 3.1 V V S it n»3'M^iY0-3l1«n'31Jlll4 nutrient analog 1^ [4] (Table3.2) (14O5±378) (in±33) > ffium© (25+13) im IT40 (166±27) > iTQ\4n?S;gn (144±83) > PTTUMQ (108±54) (85±34) uptake phase luwiha in«3Ufifii$t)3Jjjn(oi;ffsiY Yiu^ liu H 5,6,7] 208 residue Wiu'Mma9nitJMmm?imiJmfWM9fuvi(]jj 450 ° C (Table 3.3) (2.2+0.23%) > flfaumg (i.2±o.i%) f (steady state) m'nnu 63ims; 3.1 nlnmnifignaw'gawi «nunimnim j uasarm9mmj-85 i^iYi'U'ug^iJm (Fig.l) (25±6%) fnilfnsgn(13±3%) > rfTU'H'U-JSQIJflill (7+1%) (79±4%) > (hufl^fl (13±1%) > fflUHlT^JlJJfif II (5±1%) > ffTUrUB (4+3%) fn?n5Sfliau8-jSiSajj-i37 ffi (A,) fin T.F. , Tl/2una; X, (Fig.l) iftaivii^nfini'fl'UTTi^BmiimjisM^Qyti wnrni (Table 3.4) im«-3fii T.F. §5 ^S (3.2) > rfiyni^gn (2.6) > aiuMiT^^iufiiu (1.6) ~ ttTUKi (1.5) uQ^iJai^nanSfiiminij 41, 40, 42 ims 33 it 6 I^0\J M0fiilsmfuw$EJii- 5 m'iD9-3fii T1/2 [4] jfitfiufh T.F. •nnn^itu^nuo^ pfMigiiiSou-ss Sfh y nj0-3{fV159U!5fJJJ-85 1\4fTTUsU0^lJai^nfiilSfin 31,12, 4 UflS 4 -314 WiJjai^ilJ ^iT l me 209 T.F. im1/2 iii9fii'u«0imflfl'9'u[9,io] flsfif^ggiuammnfiWnu (Table 3.5) Cs Sr References T.F. K T.F. Ca 12.6±5.1 2.01 0.77 20 [9] 6.1±0.3 6.9 11.9±1.2 3.7 [10] 3.2 19 0.11 49 [this result] T.F. 11,12,13] jfivifij T.F. 30-3400 uns;u0-3fr'n50yilt)jj-8l855 SSfii l-iooo (Table 3.5) ^lTum^menKfii T.F. ^ mv\ iJfuitu < species 193n3fl§l«1 1lJuilllTn3fnEJniV1'H !j (site specific) 1i4fiTtu^wtif)inni5fin«fismHfifiS1^J l? Sl' l mSv (ICRP 60,1991) (critical group) 0 v hun49 210 ivu inaM'u^ Table 3.1 Results of physicochemcal parameters in the water during uptake period + pH Temp DO Total Total Ca K NO, Cl °C hardness solid ppm ppm ppm PPm range 5.0-8.2 25-29 5.8-20.2 100-235 734- 31-71 2.6-39 12-271 12-44 7310 mean 6.5 26.7 11.4 131 2018 49 18.8 175 24 median 5.4 26 7.8 150 1316 67 29.3 191 21.2 Table 3.2 Results of calcium and potassium in fish parts ( mg/100 g. fresh.wt.) Element skin plus fin Flesh Bone Head Ca 111+33 25±13 629±174 14O5±378 K 85±34 166±27 744±83 108±54 Table 3.3 Mean percent ash of fish parts Fish Part Ash (% of fresh wt) skin plus fin 2.15±0.22 flesh 1.24±0.10 bone 6.34+0.31 head 14.20±0.47 211 Table 3.4 Values of parameters in the mathematical model to represent radionuclide transport process at equilibrium condition, Xl Q(t) = Q( ) (1- e ) and resolved by computerized non-linear regression curve fitting procedure Radionuclide Parameter Fish Part Skin plus Fin Flesh Bone Head 137 Cs T.F., L.Kg' 1.6 3.2 2.6 1.5 T1/2 ,d 0.02 0.02 0.02 0.02 X.d1 42 41 40 33 90 Sr T.F., L.Kg' 1.0 0.1 4 17 0.17 0.18 0.06 0.02 X.d' 4 4 12 37 Table 3.5 Reported T.F. (at equilibrium) and T1/2 in the flesh offish from tropical and temperate fresh water Cs Sr References T.F. T T.F. T,fl Tropical 12.6±5.1 19+2 0.7+0.2 5±1 [9] 6.1±0.3 89+4 11.9±0.2 65±8 [10] 7.9±1.0 104±4 - 72±4 [10] 15.7+3.5 57±12 - - [11,12] Temperate 30-3400 - 1-1000 - [1] 2000 - 30 - [3] 212 100 -I 100 - (lb)Sr-85 • SKIN (l») Cs-137 iMKAl 80- 80- • • • • 78.6 + 3.9 x UONK • HEAD „ X X i M;; 60- 60- i a % X • SKIN X • MEAT 40- • 40 - xBONE 1 " R R • • HEAD 20 - " • R X 25Z6 20- X 12.5+1.0 0 - 1 1 \~—•-—H 1 1 1 1 7i' 0 - T T T T f f f days days Figure 1. Percentage distribution of Cs-137 (la) and Sr-8S(lb) in the tissues offish. The mean and Standard deviation for each tissue are also shown, average across time. 250000 -| » skin avuuu ' (2a)C»-U7 • flesh I (2b) Sr-«5 j • 200000 A bonr 40000- • * skin • head B flesh o 150000 • water • CO 30000- A bone o A • en • head • s 100000 • 20000- • water A • • • * CO • • A 50000 10000- • • A A A A • « . t ' 1 1 ; 1 » If * * t X X -9- n n 10 14 21 27 32 37 42 days days Figure 2. Concentration of Cs-137 (2a) and Sr-85 (2b) (Bq per kg.wet wt.) plotted against time of exposure in day. 213 nnnfminhsnifi nW%\i UOHOU^fU fl5. John Twinning ANSTO itasmflBQfWmfio tf1tffhlJfniJ1#1inibun?lJfn0IjiiQifl05Vn-3fTfifl f)1. Steve Sheppard fliniJ'Ul'OO A.E.C.L. ihsmffllfmuifn ta jnomjTU [1] INTERNATIONAL ATOMIC ENERGY AGENCY, Handbook of Parameter Values For The Prediction of Radionuclide Transfer in Temperate Environments 10 Draft, IAEA , Vienna, AUSTRIA (1992) [2] JANDEL SCIENTIFIC, Sigmastat for windows, Use Manual Revision SSW 1.0, San Rafael, CA , USA. (March 1994) [3] S.E. THOMSON, et al., " Concentration Factors of Chemical Elements in Edible Aquatic Organism " UCRL-50564 Rev.l Lawrence Livermore Laboratory [4] WHIGKER, F. WARD, et al., " Radioecology : Nuclear Energy and the Environment" Vol.2, CRC Press, Inc. Boca Raton, Florida [5] GUSTAFSON P.F., et al., " Cesium-137 in Edible Fish " Nature 211 (1966) [6] W.L. TEMPERATE, et al., " Accumulation of Calcium and Strontium by Brown Trout from Waters in the United Kingdom " Nature 198 (1963) [7] J.J. DAVIS, " Cesium and Its Relationship to Potasium in Ecology " in Radioecology, Sdultz, V. et al., 539 (1963) [8] S.K. ROPE, et al.," A Field Study of Ra Accumulation in Trout with Access of Radiation Dose to Man " Health Physics Vol.49, No 2 (August) pp. 247-257, 1985 137 85 [9] J.R. TWINNING and et al.," Bioaccumulation of Cs and Sr by an Australian subtropical freshwater teleost (Bidyanus bidyanus) " [10] A.S. MOLLAH et al.," Studies on Radionuclide Transfer from soil and Fresh water to the nd Foodchain of Man in the Tropical Environment of Bangladesh, Report to the 2 RCM of the IAEA CRP on Radionuclide Transfer from Air, Soil and Freshwater to the chain of Man in the Tropical and Subtropical Environment" Damascus, syria, 12-16 December 1994 214 [11] A. SRIVASTARA, et al.," Accumulation and discharge behavior of Cs-137 by Zebra fish (Brachydanio rerio) in different aquatic environments " J. Radioanal. Nucl. Chem., 138, 165-170(1990) [12] A. SRIVASTAVA, et al.," Uptake and release kinetics of Cs by Zebra fish (Brajchydanio rerio) in controlled aquatic environment" J. Radioanal. Nucl. Chem., 63-69 (1994) [13] W.A. BRUNGS," Experimental uptake of Strontium-85 by Fresh Water Organisms " Health Physics, 11, 41-46 (1965) TH9900021 TH9900021 215 i? vnalrrd mum 90112 CR-39 > 271 moiiifniwnsiTiPi viuii 1,995 + 24,483(Bq/m3) iwuSfiiWitJPl 756 ±25(Bq/m3) 244,552 ± 464(Bq/m3) ^ Radioactive Radon Gas in Ground Water in Songkhla Lake Basin Suksawat Sirijarukul Thawat Chirtrakarn and Tripob Bhongsuwan Department of Physics, Faculty of Science, Prince of Songkhla University, Songkhla 90112 ABSTRACT The technique to investigate radon concentration in water, using film CR-39 to detect alpha particle that emitted from radon gas and diffused through the water in close system, has been established. After etching process, alpha tracks were counted under optical microscope. The track density of the film gives the radon concentration level in water. From the calibration curve, the radon concentration is given by the formula. Radon concentration (Bq/m ) = Track density / 0.088137 Testing 271 samples of ground water around Songkhla Lake Basin by this method show that the average of radon concentration is 11,955 ± 24,483(Bq/m ) . The minimum radon concentration is 756 ± 25 (Bq/m ) found at Amphoe Bangkaeo Changwat Phattalung , and the maximum concentration is 244,552 ± 464(Bq/m ) found at Amphoe Namom Changwat Songkhla. 216 1 limn 3.82 iw fi^t)ii(Ra-226) 1l4ll!)91J\4l5l4^yi1TU11 ( human carcinogen ) uas 2.1 110 Trimble Navigator IM Basic Plus i\i Mettler AE200 Ra-226 21.5277 Bq/g fU.TUm 1 fluifiJJ 2540 - tnilflSNaOH - water bath iv, Grant W14 CR-39 2.2 Ra-226 500 ml 217 CR-39 nmmfw VI 1 Equation / * 00861374 ' X 1OOO i 1ODOO 20000 30000 40O0O soooc soooo Activity Rn (Bq / mA3> CR-39 inside o«"i of pot) Coffee tin IU Elastic band Clingfilm over yoghurt pot SOOgcoffte tin lined with clingfilm Tap water to be tested 218 CR-39 «/ I O n 5 2;nou9ilnifu 6 in wum CR-39 iiJnfiumoiet) *4 *=\ eime CTI^fl (Bq/m3) a;3a;fi (Bq/m1) Iflail (Bq/m3) 6,462 ± 75 65,962 ±241 20,646 ± 20,333 2,930 ±50 8,545 ± 86 5,154 ± 1,821 fll 041^14 2,930 ±50 44,770 ± 198 13,163 ± 15,793 2,567 ±47 13,254 ± 108 7,331 ± 4,667 756 ± 25 58,354 ± 226 12,439 + 17,135 1,162 ± 32 9,269 ±90 5,148 ±2,830 ihuaii 1,118 ± 31 4,832 ±65 3,383 ±1,518 2,567 ± 47 26,838 ±153 9,942 ±8,243 me-3 4,198 ± 60 21,042 ±136 9,220 ±4,681 fT?'Ufl?\4n/ 7,096 ± 79 8,545 ±86 7,820 ±1,025 3,745 ± 57 60,994 ±231 6,220 ±3,315 5,465 ± 69 19,774 ± 132 9,948 ±4,799 2,386 ± 45 19,956 ±132 6,089 ±5,560 fnuiuosi 3,835 ± 58 32,272 ±168 11,119 ±10,802 1,118 ± 31 13,525 ± 109 4,162 ±3,143 mm 2,386 ± 45 8,725 ±87 5,737 ±1,980 uini 2,205 ±44 7,729 ± 82 4,469 ± 1,678 UTHJJOIJ 2,386 ±45 244,552 +464 66,945 ±76,343 unnan 2,205 ±44 4,016 ±59 2,960 ±739 8,726 ± 87 15,609 ± 117 11,044 ±2,925 8,454 ±86 20,227 ± 133 13,123 ±4,139 fwqS 4,288 ±61 24,484 ± 146 11,443 ±7,791 1,842 ±40 13,616 ± 109 7,675 ±4,276 3,654 ± 56 39,336 ± 186 9,698 ±8,915 2,567 ±47 36,438 ± 179 8,433 ±8,758 ffsiMVIfli 1,843 ±40 16,333 ± 119 6,806 ±5,601 1,299 ±33 86,247 ± 275 12,339 ±21,214 220 1,118 ± 31 29,917 ± 162 6,969 ±7,363 3,654 + 56 6,371 ±74 5,012 ±1,921 V 756 ± 25 244,552 ± 464 11995 ±24,483 Frequency Songkhla , Patthalung .Nakorn 40 30 20 10 •~TT T nTTi ITTI •[ I'frqTrnTrTTTTrTTTTTnTn T I~T~|~T~ 0 20 60 80 100 120 140 160 180 200 220 240 Radon concentration (Bq/m) 5lJfl4 (Bq/m3) 221 5680BB 618088 888888 718888 918886 918899 B6S0SS _ 868888 810090 — S1BB8B 768098 718888 588000 G1888B 718880 Figure 5. Showing a contour map of radon concentration in ground water in Songkhla Lake Basin 222 ©=2 568888 618888 868686 718886 918688 916668 NAKllON SI KIAMM, (60888 GULF OF THAU AND — 866688 I RANI 811868 _ — 8)1166 788888 — _ 788868 718868 718806 I S88B86 618888 686666 718866 Figure 6. Songkhla Lake Basin 223 4. CR-39 YYim llfiJifUfniUl^lU'UUliPlBU^I^ 756 ± 25 Bq/mA3 , fUfl 244,552 ± 464(Bq/m3) imsSfhlttafl 11,995 ± 24,483(Bq/m3) fnfl|lJ^ 5 QimetJTHiJeiJ , 6,6945 ±76,343(Bq/m3) 2540-2541 V 6 1. C.Richard Cothern and Paul A.Rebers(1991) . Radon,Radium and Uranium in Drinking water .2nd Edition. Lewis Publishers, Inc., 1991 2. Duval, J.S., 1988. Indoor radon prediction using gamma-ray spectrometric data. EOS, Transection American Geophysical Union, V.70, p.496 l ,11-18 224 TH9900022 TH9900022 134 Cs 60 Co HTSIO uas tiviuik rmui 10140 14 ft U4Cs lias 6°Co ifltmfllTUU (Purpurascens spj 'H pH 4 5 nas 6 •qniu inuiniemwfyTmiaswuluiuYi 15 30 uas 45 srnu MOVUfil Soil-to-Plant Transfer Factor (TF) TufhuflU (TFsp) IVN1 (TFSRh) lias 11 fl 114 (TFSR) TFSP uas TFSRh 1)0-3 Cs V 1490 TFSP 1)0-3 Cs ivnuu lemm? mjuvn mfii TF uaswa« SP SP TF D0-3 '34Cs lias 6°Co : TFSR > TFSRh > TFSP TF <& ' 1 ^4 fid TF : Cs > Co SP Vl fli TFSRh lias TFSR : Cs < Co Effects of Acid Rain and Fertiliser on Root Uptake Cs and Co by Paragrass P. Chairattanamanokorn, N. W. Harvey, and O. Kerdchoechuen King Mongkut's University of Technology Thonburi, Pracha Utid Road, Tongkru, Bangkok 10140 ABSTRACT Effects of acid rain and potassium fertiliser on root uptake of Cs and Co are presented in this paper. Paragrass (Purpurascens sp.) was grown in clay soil homogeneously contaminated with the radionuclides, and kept in a greenhouse for 45 days. Plants in both fertilised and non-fertilised treatments were irrigated daily with a fixed pH solutions of 4, 5 or 6. Every 15 days plant and soil samples were harvested, and analysed to determine the Soil-to-Plant Transfer Factors (TF) of the shoots (TFSP), rhyzomes (TFSRh), and roots (TFSR). The results show that acid rain had an influence on the TFSP and TFSRh values of young plants. Application of K- 134 134 fertiliser decreased the TFsp of Cs. The effect increased with ontogeny. TF values of Cs and Co were in the order of: TFSR > TFSRh > TFSR. When compared the two radionuclides in each part, it was found that, for TFSR and TFSRh: Co > Cs, for TFsp: Cs > Co. 225 eJ 1miliJ9-3flumjih4(?lftfl(fallout) juwn (dry deposition) i V deposition) h ft It 50 % UTOinm? wimsuunn [l] Q1«liismu1?f1!nnfii Soil-to-Plant Transfer Factor (TF) TF = (Bq g"') (Bq g"') 1pifiJfm}Jit -3 mWTwa^^TuiJiinfyvii'KQi Iwiin [6,7] j Imtri diincuni9-3 clay minerals il?unfuiJi5;iDinn [8,9] nas ms:ij9 fission products ua w n\u active products 226 0-20 1 YUJTI ibsintu 2 % .7 30 gem Cs lias Co mflVJ m homogeneous 20 Bqg"' ims 18 Bqg"1 fliuaiwu Randomized Completely Block Design (3x2 factorial) 2 2 llflflU (factor) iftUfl fJuf1Ifia!'-3tft51s;vfi:»4i?l1oiJ9inni-?ll!Kfl^?n 3 ISfhj flO pH 4 5 uas 6 nasmil^tj l««l\jnpliisTs;niJ (19 gem"2) nasiiifniviwno^^iinw 2 <%-\ 30 ^^ 15 "tsu. (~o.oi m3) 36 nis pH 500 ml/TlU 15 30 ims 45 QIJ wu mlh Lias nn) yi?riumu0Hi«vj 2 85 ± 2 °c Y\ iJ?s;unfu 48 105 ± 2 °C illunai 24 SeUHTUflSUni-WUIPl 2 UamUflS 1A total activity Gamma spectrometer Ifitmilfl Ge(Tl) ^ISflil Iliinw 10 % lias; \4 Least Significant difference (LSD) 95% l34Cs ims; Co il Soil-To-Plant Transfer Factor (TF) 1v!ffQ\4PIU(TFSP) (TFSRh) 227 norm mean+SD 1. Moisture content (%) 29.09±4.19 2. Bulk density (g cm ) 1.64±0.27 3.Soil pH 3.1byH2O 5.13±O.O3 3.2 by KC1 4.18±0.03 4. Soil texture (%) 4.1 sand 5 4.2 silt 32 4.3 clay 63 5. Organic matter (%) 2.08±0.04 6. Cation exchange capacity 29.67±0.60 (meq/lOOgofsoil) 7. Total exchangeable base (meq/lOOgofsoil) 7.1 Na+ 0.90±0.06 7.2 K+ 0.57±0.01 7.3Ca2+ 14.60±0.75 7.4 Mg2+ 7.99±0.19 60 3.1 i^^ 134 Cs Co a) Cs TFSR TFSP ims TFSRh 30 (p < 0.05) \ pH 6 ri fii TF TFSRh uas; TFSP Suvnlmjimiim mo FSR 134 Tuu Cs (s?n 1HY12) 228 b) Co TF° 3.2 wfm^niiKfl&iduflm^uiJViSflQmiflA'tfiJfl'n^fl 134Cs uas a) Cs TFSP Y\ 4) lurum 30 uas 45 TU iflomoH^jtj fin TF Shhfio'liJHJ Ms DuiJBiunanmiJgninu b)60Co TF 3.3 HauQ^^lunifiimsmiHiJtji'iJiifiaiwjj^SfiQmigfi^iJffiii^^ 134Cs ims 60Co ue 3.1 uas 3.2 ifl^mi'win^QinmvnsiIsiflUDQ^pJuniPi lias (interaction) a) Cs i t 6 viuin itJivi'M 15 nas 30 fJi4nifiims;il ofltjm^l tfi3fjSHflfiefin TFSP m r\ pH 4 uas 5 iWtimiKijtjiijit-wnsnofh TFSP mv\ pH 6 SP u SP S SP SIHYI pH 6 iQunumiiiiH^JE) Iwfh TFSP fii^tjfino 0.042 uas 0.146 IUTUYI 15 uas 30 i " ^45 in Yivii fJunifiiiaj;il9«ofn5l w^w ljJff-3wa«9fii TFSRh me TFSP isM'in'aMfyiD^^'l^miasjiiji^tJ wim Sfmuu^nfii-3^ pH 5 nas; 6 ^ pH 6 iiasiiu'SfniHiJo TilITIfin TFSP fifii^tjw (o.n) tivum TFSR fmuuinnin'i^'ue^ jKi|o ilnng^ pH 4 IAUYI pH 4 nasiiiSfniH^tj Sfh TFSR g-atjpi (0.285) ^ 1IV1 1-3 b)6°Co 15 iv, •wu'ii^fiiPiimsifnii'tf^tjljjfr^HawQfin TF 30 ims; 45 iiu i^J'umfiUfCLJtJiJHmft'vnsYinn (TFSR) ^uttPi-jlu^n^i-a^ 7 229 ri pH 4 flflfltjmil^u vhlmh TFS 30 iu ^unifm-atfinsmi pH 4 imsljjlmjti qsiiifh TFSR tntjei fio 0.889 jhuYioiq 45 TU t\u ^iYi pH 5 uasiiiSmilviJo flslmh TFSR fio 0.586 ffaiilvi 3 a/ m d 114 60 3.4 minissntjemQ-aflninfl Csims Co 60 2-7 luffimsmiilgniatnnu monJitiumuufin TF UQ^ I34CS nas Co yTU'u viun mlu fin TFSP 1)8^ Cs ufnummifn TFSP UQ-3 CO ITTHIU 134 TFSRh ims TFSR "ue-a Cs Sfhuoonrifh TFSRh 11ns; TFSR 110-3 ^Co mo fin TFSR > fin TFSRh > fin TFSP l34 TFSP ims TFSRh uo-3 Cs iwow^Qi^'uo !34Cs iilu analog DO-3 fiieiiilueimwjy (K) pH 5-6 iSvi'WQ-a^mfnijniciPjfi^jj K "ointninsjfnua'ul^jjin [12] Cs flintniasaiupiu l^i^ivrwa-a pH Pi-antrnmjfTu nasiiua-ssnn Cs [13] ^YinlTiiu^oou^i^iufJunifi^ pH a^ndn Sfh TFSP ims TFSRh 60Co vnjQifmuiilvjnifiDo^fJvjijjflHfifii TF uo-a ^Co 60Co ^fl '"Co lutriifisfntjauSmo-jvHOpiofnifja^jj'UQ^ M^nutj ouijci H+ sun 60 Co Tufmasfntjfhi ^liiinni'Hm TF UO-3 60CO v 4 TFsp 1)0-3 " Cs IVITUV! ifltJ'fltl'nil'Hfli TFsp [10] o^imin l34Cs ILIUBICJ analog 110-3 K •wuiimoS K 'uw "wvmongw^jj K unnnQi l34Cs mo-jsnn K K+ 1 134 fin Cs l 230 134Cs ims ^Co luflbunu «i iie-avto •asmidi j/ ' 134 *s 1 if 60 4 eiu fin TFSP ue^ Cs ufnuinmifn TFSP IJS>3 CO TUVOIS l34 TFSR1I uas TFSR ue$ Cs Sfhueufmni TFSRh ims TFSR TF > fin TF > fin TF i l34 SR SRh SP innfm Cs mQ^ialuDinum? N2 fixation lunmie-avta 2 [11] lunjois^ 134Cs ifiaowmuiiltifff^uiiji^ [9] i^^ uas; i^iMcUTMne-3'u^fnfifT3JiJvi?i!'-3^ ai l.Schuttelkopf, H., 1998, "Determination of radionuclides in environmental samples: Behaviour of radioiodine, radiocesium and plutonium", IAEA Interregional Training Course, pp. 12-21. 2.Harvey, N.W., Shaw, G., Bell, N.J.B., 1997, "Influence of plant roots upon the mobility of radionuclides in soil, with respect to location of contaminatation below the surface", Journal of Radioanalytical and Nuclear Chemistry, Vol.226 (1-2), pp.159-173. 3.Bai-nai, T., Muramatsu, Y., Yoshida, S., Yanagisawa, Y., 1996, "Studies on the transfer of Cs, Sr, Co, Mn and Zn from soil to plants and from medium to mushrooms by using radiotracer, " NUCLEAR CROSS-OVER RESERACH International WorkshopProceedings, Improvement of Environmental Transfer Models and Parameters, Japan, pp. 181-190. 4.Rudge, S.AJohnson, M.S.,Leah, R.T.,Jones. S.R., 1993, "Biological transport of radiocaesium in a semi-natural grassland ecoststem. 1. Soils, Vegetation and Invertebrates", Journal of Environmental Radioactivity, Vol. 19, pp 173-198. 5.Malm, J., Rantavaara, A., Uusi-Rauva, A. and Paakkola, O., 1991, "Uptake of caesium-137 from peat and compost mould by vegetable in a greenhouse experiment", Journal of Environmental Radioactivity, Vol. 14, pp. 123-133. 231 6.Fesenko, S.V., Colgan, P.A., Sanzharova, N.I., Lissianski, K.B., Vazquez, C, Guardans, R., 1997, "The dynamics of the transfer of caecium-137 to animal fodder in areas of Russia affected by the Chernobyl accident and doses resulting from the consumption of milk and milk products", Radiation Protection Dosimetry, Vol 69, NO.4, Nuclear Technology Publishing, pp.289-298. 7.Salbu, B., Oughton, D.H., Ratnikov, A.V.,Zhigareva, T.L., Kruglov, S.V., Petrov, K.V.,Grebenshakikova, N.V., Firsakova, S.K., Aztasheva, N.P., Loshchilov, N.V.,,Hovel, K.., and Strand P., 1994, "The mobility of Cs and Sr in agricultural soils in the Ukrane.Belarus and Russia 1991", Journal of Health Physics Society, Vol. 67 (5), pp. 518-528. 8.Roca, M.C., and Vallejo, V.R., 1995, "Effect of soil potassium and calcium on caesium and strontium uptake by plant roots", Journal of Environmental Radioactivity, Vol.28, pp. 141-159. 9.Nisbet, A.F., Shaw, G., 1994, "Summary of a 5-year lysimeter study on the time dependent . _ 137_ 90_ 239,240_ , 241 . - , ... , transfer oi Cs, Sr, Pu and Am to crops from three contrasting sou types: 1.transfer to the edible portion", Journal of Environmental Radioactivity, Vol.23, pp.1-17. lO.Nishita, H., Wallace, A., and Romney, E.M., 1978, "Radionuclide uptake by plants", University of California, US. 11 .Marschner, H., 1995, "Mineral nutrition of higher plants", 2° ed., Academic Press Inc., UK. , 2531, \\$m\l®w\i, 13.Suvornmongkhol, N., 1996, "Uptake of radionuclides by wheat roots with respect to location below the surface", PhD.thesis, Imperial College, University of London, UK. 232 15 TU r~ fH pH 30 TU 0.18 1 0.16 -T 0.14 • 0.12 - I - - £ 0.1 X j- 1 £ 0.08 1 • • 0.06 J J.H dH- 0.04 0.02 HIi ^Hpi] ^Ts 0 _l^—L-^-^^B—[|M__MBIII—hm fin pH 0.14 0.12 0.1 H 0.08 ts—: 0.06 0.04 0.02 0 fli pH 4 5 6 >< • Cs-134 ,1 r • Cs-134 ,1lJl • Co-60 M\ mCo-60 ,1lJiiIf 134 60 TlrFs p ' Co \\iYI&~ 3*1 (mean ± SD) 233 15 1M fli pH 30 TU u. fli pH 45 VU 0.3 0.2 0.1 4 6 fli pH • Cs-134 ,1 Cs-134 , • Co-60 ,1' Co-60 . 34 6 2 llffP^fli TFSRh DB-3 ' Cs lias °Co (mean ± SD) 234 15 TU 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0 pH 30 TU u. pH 45 114 5 6 fiT pH Cs-134 ,1 • Cs-134 , Co-60 , H Co-60 , TF 'MCs UfiS ^ (mean ± SD) SR 2 fli Soil-to-Plant Transfer Factor (TF) U0-J "4 Cs pH 15 114 30 TU 45 1M. ft 14 mh nn mh nn mil nn 4 0.031 ±0.00 f 0.058+0.014' 0.283+0.0753 0.075±0.034ab 0.069±0.004a 0.177±0.058a 0.093±0.016a 0.098±0.025a 0.235±0.068a 5 0.034±0.006a 0.056±0.008a 0.290±0.115a 0.070±0.025b 0.051 ±0.010b 0.185±0.024a 0.083±0.028a 0.099±0.037a 0.176±0.026a 6 0.029±0.016a 0.060±0.000a 0.286+0.0713 0.105±0.052a 0.072±0.026a 0.194±0.025a 0.086±0.029a 0.112±0.061a 0.173±0.012a 3 fil Soil-to-Plant Transfer Factor (TF) 1J0-J '"Co 1l4VitllTU\4 ^ [i as PH 15 114 301V! 45 TU V 3/ 31 mh 51fl em nn win nn 4 0.013±0.007a 0.108±0.039a 0.660±0.077a 0.026±0.018a 0.142±0.070a 0.608±0.393a 0.018±0.007a 0. 133±0.029a 0.393±0.173a 5 0.012±0.004a 0.084±0.050a 0.611±0.254a 0.027±0.017a 0.128±0.059a 0.554±0. 127a 0.019±0.003a 0. 193±0.092a 0.502±0.099a 6 0.010±0.004a 0.117±0.060a 0.547±0.197a 0.024±0.004a 0.122±0.049a 0.496±0.089a 0.012±0.005a 0. 132±0.044a 0.398±0.131a (n= o.os) DMRT w 4 fli Soil-to-Plant Transfer Factor (TF) 1)0-3 Cs 15 ft 7>Q1M 45-114 V ?I14 Ilfl mil nn em nn 1* 0.027±0.008' 0.067±0.016a 0.311±0.104a 0.054±0.013b 0.062±0.020a 0.178±0.041a 0.068±0.012b 0.087±0.031a 0.178±0.025a 0.036±0.008' 0.049±0.008a 0.261±0.044a 0.112+0.033" 0.066±0.017a 0.193±0.031a 0.107±0.011a 0.120±0.043a 0.211±0.063a 5 fil Soil-to-Plant Transfer Factor (TF) Co D 15 11] 301114 45 114 nn em mil nn mil nn \4 0.012±0.004a 0.133±0.049a 0.713a±0.163 0.024±0.015a 0.116±0.054a 0.492±0.168a 0.016±0.005a 0.132±0.064a 0.391±0. 128a 0.011±0.006a 0.073±0.022a 0.500a+0. 130 0.028±0.012a 0.144+0.0573 0.612+0.2752 0.017±0.006a 0. 174+0.059a 0.472±0. 141a (n=6) utntiflfy (p< 0.05) Ifio DMRT 6 fil Soil-to-Plant Transfer Factor (TF) 1)0-3 WCs limahim Yl1#11J0YlSn?nj0^Umfl Uf\Z pH 15 TU 30 IV! 45 1M >< V nn mil nn 4 i* 0.030±0.002 * 0.060±0.023 * 0.264±0.115a 0.050±0.019b 0.068±0.000a 0.150±0.058a o.osilo.ooo''0 0.096±0.010a 0.184±0.052b 0.032±0.001 •" 0.056±0.002i 0.302±0.044 * 0.10010.024* 0.070±0.008 a 0.204+0.062 a 0.10610.012* 0.100±0.042a 0.285±0.034' 5 0.034±0.001 * 0.069±0.017' 0.326±0.184a 0.050±0.011b 0.049±0.014 a 0.170±0.028a 0.060±0.010c 0.087±0.047" 0.173±0.003b ml* 0.034±0.011 *" 0.042±0.001 " 0.253±0.017a 0.090±0.012 * 0.053±0.010a 0.200±0.001 ' 0.10510.017* 0.110±0.037a 0.179±0.044b 6 1* 0.017±0.003b 0.072±0.018a 0.344±0.015a 0.064±0.012b 0.069±0.037' 0.212±0.016* 0.062+0.009c 0.076±0.049' 0.176±0.015b liiW 0.042±0.011 ' 0.047±0.010' 0.228±0.037 a 0.146±0.034a 0.074±0.028 a 0.175+0.014 a o.iio±o.on" 0.149±0.058' 0.170±0.014b rtmtimw (n=2) 0.05) \?\U DMRT CO to CO 00 7 fh Soil-to-Plant Transfer Factor (TF) UfH MCo Ufl pH 15 114 30114 45 1M mil nn mil nn em mh Ilfl a j/ a a a a b a 4 I'M 0.012±0.006 0.120±0.063 0.693±0.018 0.013±0.003 ' 0.095±0.051 0.328±0.145 0.013±0.001 ' 0.128±0.004 0.261+0.093' 0.014±0.010a 0.096±0.003 " 0.627±0.114a 0.040±0.016a 0.188±0.057a 0.889±0.357a 0.022±0.007 a 0.138±0.049a 0.525+0.105 ab a »l a 5 I'M 0.014±0.006a 0.116±0.053 0.727±0.363 ' 0.035±0.025 a 0.144±0.096a 0.633±0.113ab 0.020+0.004a 0.150±0.120a 0.418±0.040abt in la 3> a a a a a IU1 a 3/ a a a a a a a ab 6 lu 0.010±0.003 0.161±0.052 0 717±0.020 0.025+0.004 0.110+0.023 0.517+0.107 " 0.014±0.008' 0.116±0.070 0.493±0.126 W la 3/ a a a a a a a bc lulu 0.010±0.006 0.073±0.013 0.378±0.025 0.024+0.006' 0.133±0.079 0.475±0.102 " 0.010±0.001 0.148±0.006 0.304±0.018 (n=2) (p< 0.05) IAO DMRT TH9900023 TH9900023 239 Cs-134 «a *j 4 iuflwj«fn n^-awm 10900 (Cs-134 Co-60) Homogeneous column experiment V 3 °KJJ. iPi^iw^nifi pH3 4.5 ims 6 iilunan 120 Co-60 Cs-134 Effect of Rain Acidity Upon Mobility of Cs-134 andCo-60 in Soil S. Ruangchuay" N.W.Harvey0) and P.Sriyotha2) King Mongkut's University of technology Thonburi, Prachautit Road, Toongklu, Bangkok 10140 (2> Office of Atomic Energy for Peace (OAEP), Vipawadee Road, Bangkok 10140 ABSTRACT This research was aimed to study the effects of groundwater and acid rain upon the mobility of radionuclides (Cs-134 andCo-60) in contaminated top soil. Clay soil was homogeneously packed in columns with dimension <|>.12.5 cm. x 50 cm.. At the top 5 cm. of the columns, soil contaminated with radionuclides was added with the same consistency. Column were kept standing for 4 months in an artificial water table kept at 3 cm. from the bottom. During this period artificial acid rain with pH3, 4.5 and 6 was applied weekly at the top. Soil samples were taken every 30 days for examination of total and extracable radioactivity. It was shown that with the aide of the rain radionuclide movement down the profile was greater, with Co-60 > Cs- 134. However acidity of the rain shown no effect on their movement. 240 1. UY1141 i V V ims;imfi^lMd^i0^fiitn?^m'HPi'Tuu fie aw 'Ha-mniJ'uiileu [l], [2] iiu miastno miiJSPii-j mi [3], [4], [5], [6], [7], [8] ^fll'lJ f^ mitrsfru im^tmi^ft \\,t\ZVilMY\^T\'f\\9\ (Total and Extracable radioactivity) fmnfia ^0 l.Free ions llflS Colloids 2.Exchange surface (Readily exchangeable ions UclS Clay-humus micells) U?l£ 3.Insoluble chimical sinks (Fixed forms Insolubke organic Hydrous oxides ims Clay minerals) °ISAY\A 3 ^0 rfTu^ l uas 2 ^^^tnjjnitiuiiilKlpiod^iiJEnn'Ufi [9] V uas mmiftninmi 241 2.1 oimee^fifny TuiPfSltasmfU 1 fllJ. Composite sample Q «" 2.2 enn-avi l YtlllV ilfmiifmswDO] Bulk density 1.178 g/cm Soil texture Clay Soil Hydrometer method Sand 5 % DW Soil Silt 32 Clay 63 Soil pH 5.13 pH meter 1:1 (Soil:Water) Organic matter 2.13 % DW Soil Walkley and Black method CEC 29.67 meq/lOOg. soil NH4OAc method Total Exchange Base 24.05 Na+ 0.89 (3.70 %) Flame photometer K+ 0.57 (2.37 %) meq/lOOg. soil Flame photometer Mg2+ 7.99 (33.22%) AAS Ca2+ 14.60(60.71%) AAS AEC 0.05 meq/lOOg. soil NH4C1 method Total Iron 2.05 mg/100 g. soil Phenanthroline method 2.3 pvc 12.5 50 2.4 Tfimh CsCi nas CoCl2 "DTUTU 0.0065 ims; 0.018 niu pnuniwu Itl 30 242 2.5 tr-a 40 PU 5 ^JJ. 5 cm. 50 cm. \/ 1 llfT1 2.6 uikfiemjuemitl'u 4 2 3 pH 3 4.5 uas 6 snuaisu 80 ua./ 3 °nj. <•• •••> O 50 cm. Ij cm . 2.7 vipme-3'Hi Extractant i Extracable radioactivity NH4C1 Y\U l M uasKnani'Ufnii'utii 30 243 2.9 inumjfl ifieauijvm 30 QU mvt 3J« 4 flf^ 11finsM Total nas; Extracable Radioactivity DO-Sfl'U 14 6 TH-3 WIIJ'pmuan m 0-5 iru . 5-10 "KU. 10-15 "WU. 15-25 "WJJ. 25-35 3. 3.1 Total radioactivity ffa 2 UftfUWUfn'nifmswVh Total radioactivity 1)0-3 Cs-134 fh Total radioactivity 119-3 Co-60 Uflffl-jVusmn-JYi 3 fl'i Total radioactivity U9-3^14 ^0 % 1)0^ Total radioactivity ^9ti1l4tKl-3fniUan V r 1 hhd^i 2 (QU^ 60 ) i ^ 3 (iu^ 90 3 Total Cs-134 UHS Total Co-60 inPlfnilfiaQliprTflin^W 0-5 "BJJ. fl9 10-15 t ti-3fi-39tj^fmuan K'u 10-15 ««JJ. fbumjYtlAiiiihpJij'vinfh pH Total Cs-134 USSTotal Co-60 fnflflUinJ 0-5 etfJJ.1lJ^^^'U 25-35 V M nuii fiifmuiil'uniPinjg-a'U'id'u ?f^wcinis;vii)9m^8'uo^nfinj 95 %) p|0ll?3J1fU Total radioactivity ffiJJIIdtYill 1^11 m9fniUtlluni^'iU9-3'U1^V!munJl4 flSPf-JWal'Hfni^S Total radioactivity Total radioactivity 1)0-3 Cs-134 ims; Co-60 INUQI 114flfms:VIA14 Total Cs-134 tms Total Co-60 (vifhfmiJilremj 95 %) nrftrfmsj^fluifiiijui^wvinfii pH BS;^U Total Co-60 TJ 244 Total Cs-134 VhmiiifmsM ^ 3 4 5 nas 6 "iraii?r?mJ?inai Total radioactivity o-5 "KU. • if i V m l}J0fmiJllll4n?A1i03'U"l^l4mU 134 3.2 Extracable fil Extracable radioactivity fl0 Extracable radioactivity ?19 Total radioactivity Extracable radioactivity wuiuflu 2 ili^fniunnmiiTu fie <%\i 0-5 •vu. ims 5-10 mi. fil Extracable Cs-134 ims Extracable Co-60 l\4finvl?lJ^ 7 llflS 8 ^nua Extracable radioactivity ue-aflnif^YUflO-aYimJ'irU 0-5 'KW. IV1TU14 V i < # fT/ms^Ruifiil'lilJifJ'lJ'Wll Extracable radioactivity U0-3a 155^ffma'8-J 2 VU \ Extracable radioactivity 110^14#14 0-5 "tilt. munilW 5-10 °KJJ. IJOfll pH f^J^ 2 (QU^ 60 as %f as d 3 OVJVI 90 ii0-3fnivi?ia0^)uasfii^a;fivnti (IUYI 120 WlJ Extracable Cs-134 114314^ 2 V i Extracable Cs-134 0-5 1JU. WnnnQ1#V! 5-10 lS^' ^ 3JU 95 %) i 3 IJJWU Extracable Co-60 1l4^l4#l4 5-10 ifW. tin ^ 4 VIUQI Extracable Co-60 nJ0^^l4#t4 0-5 TJJJ. 5-10 ^u. om-aCiItmimy (^fiifmui^aiTu 95 %) V pH WU1T Extracable radioactivity UO>aa"lif^ pH Extracable radioactivity Extracable radioactivity ^T Extracable radioactivity 1JD3 Cs-134 lias Co-60 < U'l^'U iJiUitU Extracable Cs-134 lias Extracable Co-60 ^Qlfin 95 %) u^ttnns^^viipifu'ui^vi'vinfin pH ^ 245 Extracable Co-60 Extracable Cs-134 Extracable C6-60 lifts Extracable Cs-134 2 im«-3 %fa?fVH'MJJfl(Total radioactivity)!^ Cs-134 (Mean ± SE) Time (days) Condition Depth(cm.) 30 60 90 120 No rain 0-5 97.94±o.oo722 93.15±ooo62i 96.86±o.oo353 98.43±o.oo4O8 5-10 2.04±0.00032 6.58±o.ooo98 3.01 ±0.00042 1 .49+0.00042 10-15 0.02±o.ooooo 0.27±o.oooo6 0.13±0.0O012 0.09±o.oooo8 15-25 25-35 35-45 Rain pH 3 0-5 95.24±o.oo494 96.67±o.oo35o 97.48±o.oo646 92.29±o.oo45i 5-10 4.52+0.00029 3.2O±O.OOO28 1.96±0.OO027 6.71+0.0004] 10-15 O.24±o.oooo3 0.13±0.O0OO8 0.34±0.0O015 0.62±o.oooio 15-25 0.21 ±0.00008 O.33+ooooo6 25-35 O.050±o.oooo3 35-45 Rain pH4.5 0-5 94.73±o.ooii5 9O.56±ooo624 92.16+0.01266 93.96±o.oo946 5-10 3.65±o.oooio 8.88±o.ooo92 7.61 ±0.00304 5.43±o.ooo46 10-15 1.62±0 00023 O.56±o.oooi3 O.17±O.OOO13 O.45±o.oooi3 15-25 0.06+0.00002 0.1 2±0.OOOO5 25-35 0.04±o.oooo2 35-45 Rain pH 6 0-5 94.54±o.oo326 98.51±o.oi6i5 95.98±o 00764 91.34±O.0O255 5-10 5.09±o.ooo8i 1.47±0.00062 2.95±o.ooio4 7.94±o.ooin 10-15 0.37±o.ooo2i 0.01 ±0.00001 0.93±o.ooo2o O.64±o.00005 15-25 0.15±0.0O0O3 O.O7±o.ooooi 25-35 O.O2±o.00002 35-45 246 3 UftfU %H*?tY\*m}f\ (Total radioactivity) U03 Co-60 (Mean±sE) Time (days) Condition Depth(cm.) 30 60 90 120 No rain 0-5 97.56±o.oo466 92.62+0.00100 96.66±o.ooii4 98.59±o.oo408 5-10 2.34±ooooo6 6.90±o.oooio 3.28±o.oooo7 1.24±o.oooio 10-15 0.1 O±o ooooi 0.47±o.oooo2 0.07±o.ooooi 0.17±o. ooooi 15-25 25-35 35-45 Rain pH 3 0-5 87.96±o.oo368 95.14±o.ooo87 91.80±0O0I99 87.1 l±0 00148 5-10 8.30±o.ooo3i 4.41 ±0.00022 4.80±0.00024 10.47±o.oooio 10-15 3.74±o.ooi87 0.45±o.oooo2 1.75+o.ooon 1.1 8 ±0.00002 15-25 1.65±o.ooooi 0.52±o.oooo4 25-35 0.71±0.00003 35-45 Rain pH4.5 0-5 90.09±o.ooo34 89.82+0.00051 84.97+0MI56 90.37±o.ooioo 5-10 7.21 ±0.00021 9.44+0.00033 13.31 ±0.00024 7.81 ±0.00024 10-15 2.70±o.oooi6 0.74±o.oooo7 1.21 ±0 00003 1.04±0 00008 15-25 0.50±o.00002 O.45±o 00008 25-35 0.33±o.oooo2 35-45 Rain pH 6 0-5 88.59±o.ooo24 93.96±o.ooi2o 85.26±o.ooo4o 85.O8±o.ooii7 5-10 10.17±0.0O039 5.60±0.00097 10.53±o.oooo8 12.60±0.00066 10-15 1.24±o.ooooi O.44±o.oooo5 2.78±O.OOOII 1.71 ±0.00007 15-25 1.43±o.oooo4 0.24±o.oooo2 25-35 O.37±ooooo3 35-45 247 I Cs-134 Co-60 pH3 pH4.5 3 utTfl-3 % Total radioactivity Cs-134 ims Co-60 Ylfmtmn 0-5 °W3J. Y\nm 30 80 pH3 pH4.5 pH6 T\\Y[ 4 UttfU % Total radioactivity Cs-134 ims Co-60 Ylfmuafl 0-5 °BU. Vinai 60 100 97.48 95.98 :|95 91.8 92.16 CD • CO 84.97 85.26 £85 -I 80 1 1 pH3 pH4.5 JpH6 1"\\Y\ 5 Hfffl-3 % Total radioactivity Cs-134 UfiS Co-60 0-5 ^JJ. Ytilf\-\ 90 111 Cs-134 Co-60 80 pH3 pH4.5 6 UflffU % Total radioactivity Cs-134 lias Co-60 VlfniJJfin 0-5 «K3J. 120TU 248 I No (0-5) HNo(5-10) BpH3(O-5) HpH3(5-10) • pH4.5(O-5) B pH4.5(5-10) • pH6(0-5) BpH6(5-10) 30days 60days 90days I20days %Extraction of Cs-134 lNo(0-5) UNO(5-10) pH3(5-10) • pH4.5(0-5) H pH4.5(5-10) • pH6(O-5) IJ pH#5-10) 30days 6Odays 90days 120days 8 UPffi-3 %Extraction of Co-60 « n?^ini4fnivian1'unT3tfi3ai4^'U0^?fi?i-3ffliJtTfms;w i i 2. ^0 l. (Mass flow) 2.mitm5 (Diffusion) 3. 249 (Mechanical mixing) 4.milfl^9W^lflt)^-3SSl« (Biological transfer) 2mtn 2 rnsiiTumiYimAiJulfli fi9 m? imsrmum t y nnmj'uu 3. V (Total radioactivity liflSJ Extractable radioactivity) imSYHiWtflJA (Cs-134 ims Co-60) » y v 1 ^-nimi^ntJifli-JW Sfil CEC ^^ ^ff^HfilM Buffer capacity y pH De^Ui^ 4. Co-60 ifiPiaufi'QiiJWfluwiuani^nii Cs-134 ma-amn Cs-134 fjn^f^iQny u clay 1 1 y y mineral °K-3^U^1llv!fn?^nyifl1-3'S 8 % clay ?NUin (63 %) fl-atiilM Cs-134 Co-60 5. na^D9fifnnfTjjjjw?if>33 uamf 6. 1. Alloway, B. J., 1990, Heavy Metals in Soils, New York, Halsted Press John Wiley & Sons, Inc., pp. 7-27. 2. Bunzl, K., 1990, "The Migration of Radionuclides in Soil," Proceeding of the Second International Summer School : Low-level measurements of man-made radionuclides in the environment, 25 June - 6 July 1990, Spain, pp. 329-353. 250 3. Howills, G., 1995, Acid Rain and Acid Waters, 2nd edition, New York, Marcel Dekker, Inc., pp. 1-237. 4. Kennedy, I.R., 1992, Acid Soil and Acid Rain, UK., Galliard Printers Ltd., pp. 1-159. 5. fiim ijjusmni, 2538, , iviuniJwiiinJi?yEynivimfntTfliiivniJcywi j, 127 wui 6. Gary, M. P., Sims, J. T. and Vance, G. F., 1994, Soils and Environmental Quality, London, Lewis Publishers, pp. 249-257 7. Greg, O. H., 1989, Soil, Vegetation, Ecosystems, Hong Kong, Oliver & Boyd. Pp. 157-162. , 2535, i^TKimiiiow'u, mmfif-avi 7 , li^'mrmnumm, 730 •H141. 9. ffnuin vm^flffiAwajin, 2539, 1, 327 V(U1 'H fin riis tin UAS ijomS, 2536, 2, mimifmifryeii, viww 1-32 TH9900024 TH9900024 251 14c-Endosuifan \mw viwm aipniWNfifii1 ymal "Hfifu2 was iH 14c-Endosulfan I4c-Endosuifan MC-Endosulfan flfnimjfafffl 0K-3f11^1fiitt9flfia8-3n'Ufl'ifmJJ«BUcK11l 14 Mobility and Distribution of C-Endosulfan in Soils Patana Anurakpongsatorn , Pannee Pakkong and Preeda Parkpian Dept. of Environmental Science, Faculty of Science, Kasetsart University Dept. of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University Environmental Engineering Division, The Asian Institute of Technology ABSTRACT Chromatographic packed-soil Column was used to study the relative mobility and distribution of endosulfan in soil. With water saturated flow and gravity, Phrabat soil (PakChong Series) showed much more relative mobility and distribution than Rangsit soil (Rangsit Series). This was agreed with soil permeability of the two soils with were 0.34 and 9.16 mm/hr for Rangsit soil and Phrabat soil, respectively. This result was in agreeable with the adsorption coefficient (kj of the two soils which was higher in Rangsit soil compared to Phrabat soil. The distribution of endosulfan was found mostly in the top 10 cm of soil. As expected distribution to deeper extend was observed in Phrabat soil. 252 gag 1. INTRODUCTION Soil, as a major sink for chemicals treated directly to soil or entering indirectly to- soil in some other different ways such as dipping to soil during crop spraying program or through crop residue of treated plant falling to the soil or even by accidentally spilled. Soil types and soil environments play an important role in mobility and distribution of chemicals reach to soil. Laboratory study of mobility and distribution of chemicals serves for the prediction of behavior of chemicals in the field conditions. 2. METHODS 2.1 Chromatographic Packed-Soil Column Glass columns, 2.5 cm in diameter and 24 cm in length, were uniformly packed with homogeneous plow layer soil which had been air dried and sieved through 200 JJ,m. A 100 g of Rangsit soil was needed to attain the soil length of 20 cm, while Phrabat soil was only 150 g to attain the same level. The density of these two samples was found to be 1.02 and 1.53 g/cm for Rangsit soil and Phrabat soil, respectively. Duplication were conducted for each type of soil. Soil column was saturated with water and 14 stabilized overnight. C OC-Endosulfan was applied at 0.575 JJ,Ci on the top surface soil in each columns and was left overnight. Then each soil column was eluted with water by gravity.drain. The amount applied were equal to 1.63 Llg/g soil and 1.09 JUg/g soil for Rangsit and Phrabat soil, respectively. The soil columns were allowed to drain for 24 hr. Leachate was collected in fraction at the volume of 100 to 200 mL. One milliliter of leachate fraction was counted for C by adding 10 mL scintillation cocktail (Highsafe 3, Wallac Company, UK), shaking vigorously, leaving in the dark overnight and counted for C activities using Liquid Scintillation Counter (LSC, Wallac 1220 Quantilus, Ultra Low Level Scintillation Spectrometer). After stopping leachate collection, soil column was then sectioned into 4 sections, 5 cm 14 each in length. Soil sample was air dried in the fume hood and determined the amount of C-Endosulfan in each sections. 2.2 Extractable Portion A 2 g of air-dried soil was extracted with 10 mL methanol by shaking at 350 rpm for 2 hr and was left to settle overnight. The methanol solution was, then, collected. Extraction was repeated 3 times, all 253 methanol solution was combined. Three milliliters of methanol solution was taken to count for C activity using LSC. 2.3 Unextractable Portion Soil residue after removed of all methanol solution was left to dry in the fume hood. A 0.5 g of soil residue was taken into ceramic oxidizer boat, the equal amount of cellulose powder was added and mixed well. The soil was combusted in biological oxidizer (OX-500 Biological Material Oxidizer, R. J. Harvey Instrument Corporation) for 4 min. CO2 was trapped in biological oxidizer scintillation cocktail and counted for C activity using LSC. 3. RESULTS The results of 70-day experiment showing endosulfan mobility in chromatographoic packed-soil column were presented in Table 1. Table 1 Cumulative Concentration of Endosulfan in Leachate and Distribution of Endosulfan in Two Different Types of Soils Leachate (% of Applied) Soil Distribution (% of Applied) Cum Cum Cum% Mean Weight (g) Extrac Unext Total % Sample Leachate(mL) dpm Depth (cm) Rangsit Soil 100 nd nd 0-5 34.40 68.09 22.08 Column 1 200 68 0.005 5-10 25.93 6.39 3.12 300 352 0.030 10-15 17.50 * * 400 746 0.060 15-20 18.37 * 500 1407 0.110 99.79 Rangsit Soil 100 nd nd 0-5 24.75 60.94 21.54 Column 2 200 76 0.006 5-10 17.44 3.80 1.82 300 380 0.030 10-15 27.91 0.83 0.29 420 1880 0.150 15-20 29.57 0.43 0.08 89.73 note recovery of unextracable portion exceeded 100 % 254 (Cog) Table 1 Cumulative Concentration of Endosulfan in Leachate and Distribution of Endosulfan in Two Different Types of Soils (Continued). Leachate (% of Applied) Soil Distribution (% of Applied) Cum Cum Cum% Mean Weight (g) Extrac Unext Total % Sample Leachate(mL) dpm Depth (cm) Phrabat Soil 100 nd nd 0-5 45.36 52.00 20.00 Column 1 200 176 0.014 5-10 36.43 13.00 5.13 300 1184 0.090 10-15 22.11 4.42 1.63 400 2464 0.190 15-20 25.19 2.59 1.18 500 5584 0.440 116.18* 700 10459 0.830 900 15949 1.260 1100 20259 1.600 1300 31239 2.470 1500 48414 3.830 1700 69795 5.510 Phrabat Soil 100 nd nd 0-5 35.08 52.55 14.81 Column 2 200 248 0.020 5-10 29.75 8.16 2.79 300 1305 0.103 10-15 29.77 4.86 1.87 400 2985 0.240 15-20 35.78 3.27 1.35 500 5985 0.470 97.73 700 10235 0.810 900 14985 1.180 1100 20145 1.590 1300 245825 1.940 1500 35583 2.810 1700 47703 3.770 1900 59132 4.670 2100 70032 5.530 2300 82332 6.500 2500 97037 7.670 2650 102112 8.070 Note: nd=non detectable, "=less than 0.001, Cumu=Cumulative, Extrac=Extractable portion, Unext=Unextractable portion, amount applied=0.575 (iCi per column, 1 p.Ci=2.2X lo'dpm @°g 255 4. DISCUSSION AND CONCLUSION Table 1 showed the cumulative concentration of endosulfan in leachate and the distribution of endosulfan in two different types of soil. From the first 200 mL of cumulative leachate, the one from Phrabat soil column showed the higher concentration of endosulfan than that of Rangsit soil column. Leachate flow was reduced with time. Phrabat soil had much better continuous flow. The total cumulative leachate from Rangsit soil column 1, column 2, Phrabat soil column 1, and column 2 were 500, 420, 1700, and 2650 mL, respectively. Using the modified techniques of Weber and Keller (1994) with an assumption that the moving distance of endosulfan in leachate was 25 cm, comparison in terms of relative mobility (Rj) between the two soils were shown in Table 2. Two main factors influencing the mobility of pesticide in soil are adsorption and mass flux (Scheunert, 1993). These two factors were used for further discussion. 1. Adsorption: The affinity as adsorption of chemical to soil reduced the possibility of them to move away from the original site. Adsorption coefficient Kiuji of endosulfan to Rangsit soil and Phrabat soil were 0.14 and 0.12, respectively. However, when normalized KiKls to Kx, Km of Phrabat soil (7.44) was higher than that of Rangsit soil (6.73) (Parkpian et al., 1998). According to the results, adsorption process in this case may not be a main factor directly involved in the difference of mobility in the soil samples. 2. Mass flux: Mass flux of dissolved fraction in solution consisted of diffusion, convection, dispersion, and removal processes. 2.1 Diffusion, which was a factor independent on water flow, can be described by Fick's law of diffusion as follows: J= -D5C aT Where J = quantity of transport per unit across sectional area per unit time D = diffusion coefficient c = concentration x = the space coordinate measured normal to the section 256 The main parameters that influence the diffusion of pesticide are adsorption, soil water content, temperature, and bulk density. Adsorption has already mentioned above, while temperature is at the same condition as well as soil water content in this condition which was water saturated. Difference in bulk density between two types of soil can be considered for influencing the mobility of endosulfan in soil column. Soil with more pore space to soil particle, classified to be low bulk density has a high leaching potential.' Phrabat soil has a high value of bulk density than Rangsit soil. That should make endosulfan more leachable in Rangsit soil column than in Phrabat soil column, but the result was reversed. That can be explained by using multiple parameters such as soil texture, and distribution of three phases of solid, water, and air. However, Phrabat soil has higher in permeability than Rangsit soil. Phrabat soil is classified as clay-loam whereas Rangsit soil is clay. Since clay content of Rangsit soil was about two times higher than Phrabat soil. Further the nature of clay, fine soil particle, has a good character in swelling when wet, and this expanding phenomenon reduced amount of soil porous. In addition sand content in Phrabat soil, can contribute to more pores between soil particles in Phrabat soil when compared to Rangsit soil. The greater number of soil porosity, the higher possibility of mobility of endosulfan was in soil. Moreover, the ratio between solid phase to air phase of Phrabat soil was greater than Rangsit soil, this was enhancing the mobility. 2.2 Convection was dependent on water flow. Darcy's law was used to estimate the amount of water that can be transported away from the original point. v= -ks where v = velocity of flow k = coefficient of permeability, hydraulic conductivity, effective permeability, seepage coefficient s = hydraulic gradient when concerning on flow rate, Q = Av = -Aks where Q = flow rate A = cross section area The factors influencing k were size characteristic of porous medium and properties of fluid (water) 257 Table 2 Relative Mobility of Endosulfan in Chromatographic Packed-Soil Column Sample D(cm) F MI (DXF) Rf (SMI/Max D) Rangsit Soil Column 1 2.5 0.9 2.25 7.5 0.10 0.75 12.5 <0.001 0.13 17.5 O.001 0.018 22.5 0.001 0.023 0.14 SMI 3.054 Rangsit Soil Column 2 2.5 0.92 2.3 7.5 0.06 0.450 12.5 0.01 0.125 17.5 0.01 0.175 22.5 0.002 0.045 SMI 3.095 0.14 Phrabat Soil Column 1 2.5 0.68 1.7 7.5 0.17 1.275 12.5 0.06 0.75 17.5 0.04 0.700 22.5 0.05 1.125 EMI 5.55 0.25 Phrabat Soil Column 2 2.5 0.69 1.725 7.5 0.11 0.825 12.5 0.07 0.875 17.5 0.05 0.875 22.5 0.08 1.8 EMI 6.1 0.27 Note: D =mean mobility distance, F=fraction of endosulfan in soil, MI=mobility Index, Rf=relative mobility of endosulfan 258 The relative mobility (Rf) values in Table 2 showed that Phrabat soil had higher permeability than Rangsit soil. This agreed with permeability data of the two types of soil were 0.34 mm/h in Rangsit soil when compared with 9.16 mm/h in Phrabat soil (Parkpian et al., 1998). 2.3 Dispersion can be expressed in the same manner as diffusion but in the non-uniformity of velocity distribution that results from the characteristics of flow through narrow pores and from the complex geometry of the pore system. In dispersion, tortuousity coefficient as well as flow velocity is involved. Dispersion Equation described for dispersion are shown as follows dc = dt dx2 where Da . Otv +X,D Ot = dispersivity v = flow velocity A = tortuasity coefficient Da = the coefficient of molecular diffusion Based upon Phrabat soil properties, diffusion of endosulfan both in lateral and downward movement (mobility) was much higher than in Rangsit soil. 2.4 Function of removal of pesticide by biological and/or chemical reactions can be defined as degradation. In this experiment, radiolabelled compound was used as a tracer to study the mobility. However, only total activities were quantified did not distinguish between parent compound and degradation products. Whereas volatilization of endosulfan in this study was neglected due to mainly to the soil columns were kept under saturated condition. 259 5. ACKNOWLEDGEMENT The authors wish to express sincere thanks to The Royal Thai Government scholarship, to Kasetsart University and to PHP Institute for their partial financial support of this research. 6. REFERENCES 1. Parkpian, P., Anurakpongsatorn, P., Pakkong, P., and Patrick, W. H. .J. Environ. Sc. Health, B33(3), 1998:211-233. 2. Scheunert, I., Fate of Environmental Chemicals in Soils, Plants, and Aquatic Systems. Boca Raton, Lewis Publishers. 1993: 1-22. 3. Weber, J. B., Mechanisms of Pesticide Movement into Ground Water. Boca Raton, Lewis Publishers. 1994. 15-42. 260 wowi thnnu uasiJjw nviu.i 10900 \m. 579-5230 W8 511 lvi5Pfl? 561-3013 IOO, loo ims 93.28 ± 0.09 % hV# ifl Cs-137 Co-60, Cs-134 ims; Sr-85 V 0-40 O.69 28 TIU 50°c o, o.i, 0.2, 1,2,3,6,7, 10, 14,21 ims30TU « 9«ititT^uwtnju9^fU9mfii1i4m95iJj'u«n^miJis;injm'inii 20% Co-60 tins; Sr-85 f Cs-134 wuQi59mim?ifm9U«ioflpm<3fliiJ5sus:n?n ?fivi Cs-137 2 Ill III! !•!'• •••" -••" TH9900025 TH9900025 261 Leaching Studies of Radioactive Cobalt, Cesium and Strontium of Cemented Sludge from Liquid Waste Treatment Plant Monta PUNNACHAIYA, Fookiat SINAKHOM and Pathom YAMKATE Radioactive Waste Management Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok 10900 Tel. 579-5230 ext. 511 Fax. 561-3013 ABSTRACT The chemical process used for treatment of Co, Cs and Sr contaminated in radioactive liquid waste at OAEP yield 100, 100 and 93.28 ± 0.09 percent recovery. The chemical sludge remaining composes only very slightly of Cs-137. The chemical sludge used in this study were spiked with radioactive tracers of Co-60, Cs- 134 and Sr-85. Cemented waste forms were prepared for 0-40%waste loading with 0.69 water to cement ratio and tested for compressive strength after curing for 28 days. Leaching studies via water at ambient temperature and at 50°C were performed within the duration of 0, 0.1, 0.2, 1, 2, 3,6,7, 10, 14,21 and 30 days. The results revealed that compressive strength decreased with the greater % waste loading. The optimum sludge loading was 20%. There were no leaching of Co-60 and Sr-85 in any % waste loading at both temperatures while Cs-134 was decreasingly leached upon the time, Cs-137 was slightly leached after 2 weeks and gradually decreased afterwards. 262 UTTWI i'u 3 itasmi inn9 nwinmiwui wgmin^ni viu vnu?i9tniifi3 263 JU «n Tm 300 Kg/cm2 (me 5 - 30 MN/m2) ^5uviniJii9i4iii) V V 2 ibsfrnfis l. iw *=» a"=» 2. V ta 15 - 40 % 28 3. 4. m9^n'wiv(q^fiiiijfn?ma0V!tinfj 5. imsvi 50°c 6. o 4096 2. ( Jar Tester) VI1OJJi 3. 1.5 4. 300 5. o-i nltmfu 6. ^ 7. Water Bath 8. Desiccator io. 11. Co-60, Cs-134 ims; Sr-85 12. tniasmwue^ CoClr6H2o, CsNO3nas SKNO3)2 aoiPiioutni^saiwlTiSfniui^u'uu 2,000 ppm 13. fmiflfiei'U'n ^0 Na3PO4.12 H2O, Ca(OH)2, K4Fe(CN)6.3 H2O, CuSO4.5 H2O, Fe(NO3)3.9 H2O, NaOH, 0.1 N HNO}, DDTC(Diethyl Dithio Sodium Carbamate) Uf»S Bentonite 14. niS V 15. iS (§°g 265 16., fmUIY-35.5 Tttl. 18. cnfigfjflmtJjj^THfuitt^iQgdi^fnnfisfigtimS 19. finifi9i uvnufhfTU nisijgnen^ nwvj9fiSmfju^TH'5'iJu?i-3vi'un§m\4P) panchet 20. uiflunmuipifmjjsj 500 fM.^ 21. •uQfivifnfT^fi'utJififniJj^ 250 ftu.inj Co-60 , Cs-134 uas; Sr-85 4096 3. 3.1 Wf1WS;n0ulflll0aWfl'3t)lS Cobalt Precipitation 3.2 «fl?lSf10'u5l5t)lJpilltJQB Copper Ferrocyanide Coagula 3.3 einflSfl0UfrV)10Ul5mJ&)tni5 Phosphate Coagulation 4. 5. ff x loo Cs-137 mni unsSiJiJjifu^i ^•iTvifl^wo^iwujnsnujj'upif^^wpifnjj'uo^ Co-60, Cs-134 uns Sr-85 266 Cs-137 60-80 °c v v i v l. iHi%flinumjm0iJiDnaiuifidlum9§mufl s 6 i^uinnn (%) m0cKiui4(n 0.256 ± 0.009 fnnwsfiouififlsnnlmiuiJTuVifnnmQ^mjni 93.380 ±0.134 • 2. 15, 20, 24, 30, 33 3. Co-60, Cs-134 ims Sr-85 mulilmnu l ^ SV tilii Blank Cs-137 4. oumn?i 0.69 % mnnrncwinij % thiilfl % lUcHflUUfl 15 34.60 50.10 20 32.66 47.34 24 30.98 45.16 30 28.58 41.42 33 27.40 39.80 40 24.50 35.50 5. i3i 267 Blank 6. wan uehwQwu'iehoo'uTmfmj uasfWYis'H24' 7. niMUfivtunoia floiifmuyi'uiii-affa^fiAs 4-5 wioih-a 8. unsuimvia'0'waia'pifi00fi nas^'n^l^oQi'HnSiio-Juiu 28 i\i( (ui«vishimadzu) vxiwYiim 1.15 l. M^snfiisusna'mufn 28 q 400 aiJ.'KU. mo^fitJTwqwniDJiiasennmitnaeutim'us^a'iinjjjJuwi^a Co-60, Cs-134 ua i i Sr-85 ^0tWHfjCw0-3Ufls;^ 50 ° C 2. inuwiom^'uiflifiinpi 200 au.'flw. iiJpiiTo^iliuifui-j^isitJ^nai 0, 0.1, 0.2, 1, 2,3,6,7,10,14,21 nas; 30 iv. 3. inTUQtU9(?inmilfia0UmtJ^0-3a'1inU3JVl?i!'^^I?iyiB Paige Leach Test Leach Rate (LR) = At. Wo g/cm2. d Ao. S.T • 1 V i3J9 Ao = At = iJfjJioi^^ifiaouSitJoonininnwawrfunininiliJistisnai T Wo= S = •wufiNTKn'HUfl'iiO'Wioth-a (cm ) T = iso 4. ^nuifnima0wmt) 5. 6. v ^^ 1-6 268 flmmOH WHUJJ ims Co-60, Cs-134, Cs-137 s; Sr-85 s Sr-85 mni Cs-i34ims Cs-134 ims Cs-137 3-8 9-11 Cs-134 ims; Cs-137 mmzuznm 20 % nas 40% 2 Cobalt Precipitation Ifll 100% Copper Ferrocyanide Coagulation 1« 100 % Phosphate Coagulation Ifi 93.28±0.09% osphate-Iron Coagulation 28 TU iflu 251.10 ± 20.09 Kg/cm2 *• 150 Kg/cm2 uu 20 % 5B-3flfiiSu0?in?Tii4Wprjj^i'Huis;it}jaivifiJfniw5nm0fnnciTrufliii 269 nil Cs-134 ffiviCs-137 50°c Cs-134 ims Cs-137 j Cs-134 Cs-134 Cs-137 ri 20 tl Cs-134 20 150 Kg/cm2 24 % V V 150 Kg/cm2 1. Hideo Matsuzuru, Noboru Moriyama, Yoshiki Wadachi and Akihiko Ito; Leaching Behaviour of Co-60 in Cement Composites; Atomkernenergie (ATKE), 1977 , 287-289 2. Hideo Matsuzuru, Noboru Moriyama, Yoshiki Wadachi and Akihiko Ito; Leaching 270 Behaviour of Cesium-137 in Cement-Waste Composites; Health Physics Pargamon Press, Vol.32 (June), 1977 ), 529-534 3. Hideo Matsuzuru; Leaching Behaviour of Strontium-90 in Cement Composites; Annals of Nuclear Energy, Vol.4, 1977, 465-470 4. J.A.Ayres; Decontamination of Nuclear Reactors and Equipment; The Ronald Press Company, New York; 1970 5. Judy F. Sese " Motar and Concrete Theory, Concrete Control and Testing " IAEA Regional Training Course on "Management of Spent Radiation Sources and Other Waste from Small Nuclear Applications" at Philippine Nuclear Research Institute, Manila, Philippines; 23 January - 10 February 1995 6. M. Punnachaiya, P. Yamkate; Study on Detergents Efficiency in the Radiactive Decontamination Process; Proceedings of the 4 Nuclear Science and Technology Conference, Bangkok, Thailand; 20-22 October, 1992 7. Takashi Matsumura, Toshio Ishiyama, Takashi Karino and Tetsuo Mamuro; Study on the Treatment of Radioactive Waste Water by Flocculation; Radiation Center of Osaka Prefecture, Sakai, Osaka, Japan; Vol.2, 1961 8. Conditioning of Low and Intermediate Level Radioactive Wastes, IAEA-Technical Report Series No.222, IAEA, 1983, 175 9. Flocculation and Coagulation of Liquid Radioactive Waste ( Technical Paper ); Radioactive Waste Management and Decontamination Division, Oarai Research Establishment, Japan Atomic Energy Research Institute, Japan; 1996 10. Liquid Waste Treatment of JAERI; Radioactive Waste Management Division, Department of Decommissioning and Waste Management, Tokai Research Establishment, Japan; April 1993 11. Standard Test Method for Compressive Strength of Cylindrical Concrete Specimen, ASTM Designation : C39 American Association State, Highway and Transportation Officials Standard, AASHTO No. : T22 , June 1986, 25-30 12. Treatment of Spent Ion Exchange Resins for Storage and Disposal, IAEA- Technical Report Series No.254, IAEA, 1985, 19 13. iI'UYmifu osmhjsn uas IJJJJ imuumq " niiibsqnwl#flhiuamiJatn4''lt)eei4 271 ^vrm-anidYivmyitnat) tl 2535 14. 1J3U ims ihjvniiai 15. uaj 16. uon.409 1J2525 wui 1-16 3oms aisinij PH tfiinudv) iJsranomw aisnuiJURso3 lums fSnnmnau nnffcfidu Cobalt Fe(NO3) 3-9 H2O ( Fe 30ppm) 10- 11 Co-60 100 Precipitation NaOH 7-9 DDTC lOppm 7-8 Copper K4Fe(CN)6.3 H2O ( 40 ppm ) 5-6 Cs-134 100 Ferrocyanide Coagulation CuSO4.5 H2O ( 50 ppm ) Bentonite ( 50 ppm ) Phosphate Na3PO4.12H2O(800ppm) 10 Sr-85 93.28^0.09 Coagulation Ca(OH)2(180ppm) % woomneirnauluHaDinnjiimnM nynrmjusjiTfl ( Kg/cm2) 0 251.10+ 20.09 15 166.67+ 15.70 20 150.00+12.60 24 133.33+ 13.50 33 110.00 + 9.50 40 83.50 + 8.70 272 Cs-134 15% Leaching Time Activity LR x 103 Activity LRxlO3 (d) (At, cps) 25°C (R/cm2.d) 25°C (At, cps) 50°C (g/cm2.d) 50°C 0 Ao=487.30+6.10 0 Ao=495.40+1.80 0 0.1 0.11+ 0.01 3.14 0.32+ 0.01 8.97 0.2 0.42+ 0.03 5.63 0.65 + 0.01 8.58 1 1.08+ 0.06 2.46 1.56+ 0.07 3.50 2 1.48+ 0.01 1.69 2.11 + 0.04 2.37 3 1.71 + 0.08 1.30 2.75 + 0.08 2.06 6 1.82+ 0.13 0.70 3.42+ 0.07 1.28 7 2.32+ 0.16 0.76 3.63+ 0.18 1.16 10 2.63+ 0.02 0.60 3.88+ 0.22 0.87 14 2.84+ 0.06 0.46 4.89+ 0.25 0.78 21 3.41 + 0.27 0.37 5.57+ 0.06 0.59 30 3.58+ 0.27 0.27 5.96+ 0.20 0.45 Tsmae'umrj'ua^aii nmrupmt Cs-134 fSaVrnffTuwarmieuruemn Leaching Time Activity LR x 103 Activity LR x 103 (d) (At, cps) 25°C (g/cm2.d) 25°C (At, cps) 50°C (g/cm\d) 50°C 0 Ao=15.41±0.13 0 Ao=15.44±0.03 0 0.2 0.14 ± 0.004 30.60 0.57 ± 0.01 124.35 1 0.45 ± 0.01 16.72 1.19+ 0.03 44.14 2 0.75 + 0.05 13.94 1.49+ 0.01 27.63 5 0.94+ 0.04 6.99 2.01 + 0.02 14.91 7 1.07+ 0.02 5.68 2.02 + 0.02 10.70 9 1.18 ± 0.01 4.87 2.02 ± 0.06 8.32 12 1.20+ 0.06 3.72 2.03+ 0.13 6.27 14 1.20 ± 0.02 3.19 2.04+ 0.12 5.40 21 1.33+ 0.15 2.35 2.36+ 0.01 4.17 30 1.40± 0.01 1.73 2.41 + 0.03 2.98 emi-sri 5 aemniiifiae Leaching Time Activity LR x 103 Activity LR x 103 (d) (At, cps) 25°C (g/cm\d) 25°C (At, cps) 50°C (K/cm2.d) 50°C 0 Ao=427.01+3.27 0 Ao=426.28+2.38 0 0.1 0.12+ 0.01 3.46 0.43+ 0.01 12.40 0.2 0.29+ 0.01 3.93 0.67+ 0.01 9.10 1 0.89+ 0.01 2.05 1.61 + 0.03 3.72 2 1.47+ 0.01 1.69 2.73 + 0.07 3.15 3 1.84+ 0.04 1.41 2.81 + 0.07 2.16 6 2.61 + 0.02 1.00 3.92+ 0.11 1.51 7 2.87+ 0.04 0.95 4.03 + 0.002 1.33 10 3.10+ 0.09 0.71 4.52+ 0.13 1.04 14 3.58+ 0.17 0.59 4.92+ 0.18 0.81 21 3.90+ 0.08 0.43 5.26+ 0.10 0.58 30 4.17+ 0.19 0.32 5.40 ± 0.01 0.42 273 Cs-134 30% Leaching Time Activity LR x 10"3 Activity LR x 103 (d) (At, cps) 25°C (g/cm2.d) 25°C (At, cps) 50°C (g/cm2.d) 50°C 0 Ao=14.06±0.08 0 Ao=13.91±0.50 0 0.2 0.14+ 0.02 25.84 0.41 + 0.02 76.50 1 0.36 + 0.02 11.30 0.89+ 0.01 28.23 2 0.44 + 0.02 6.90 1.07+ 0.01 16.97 5 0.56 + 0.06 3.52 1.02+ 0.04 7.61 7 0.65+ 0.01 2.91 .30+ 0.06 5.89 9 0.72 + 0.02 2.51 .44 + 0.02 5.08 12 0.72+ 0.01 1.88 1.44+ 0.02 3.81 14 0.73 + 0.09 1.64 1.44+ 0.03 3.26 21 0.76 ± 0.03 1.14 .50 ± 0.07 2.27 30 0.77 + 0.02 0.81 1.53+ 0.01 1.62 r Tsiflaowmauosieni mwimemff Cs-134 fiefemafTUHau'Ufnmomni 33% Leaching Time Activity LRxlO"3 Activity LR x 10J (d) (At, cps) 25°C (g/cm2.d) 25°C (At, cps) 50°C (g/cm2.d) 50°C 0 Ao=235.22+3.66 0 Ao=227.37±1.28 0 0.1 0.09+ 0.01 2.59 0.28 + 0.02 8.33 0.2 0.26+ 0.01 3.52 0.49+ 0.04 6.86 1 0.43 ± 0.01 0.99 1.10+ 0.06 2.62 2 0.50+ 0.01 0.58 1.22+ 0.004 1.45 3 0.57+ 0.04 0.44 1.52+ 0.11 1.21 6 0.88+ 0.03 0.34 1.76+ 0.05 0.70 7 0.93 + 0.05 0.31 1.81 + 0.05 0.62 10 1.05+ 0.04 0.24 2.03 + 0.03 0.48 14 1.20+ 0.07 0.20 2.03 ± 0.08 0.35 21 1.20+ 0.11 0.13 2.06+ 0.12 0.23 30 1.20+ 0.08 0.09 2.11 + 0.04 0.17 wm-afi 8 Cs-134 40% Leaching Time Activity LR x 103 Activity LR x 10 3 (d) (At, cps) 25°C (g/cm2.d) 25°C (At, cps) 50°C (g/cm2.d) 50°C 0 Ao=15.40+0.57 0 Ao=l 5.14+0.49 0 0.2 0.26 ± 0.01 38.41 0.65+ 0.04 97.68 1 0.39+ 0.02 9.80 1.54+ 0.07 39.34 2 0.54 ± 0.01 6.78 1.93+ 0.02 24.65 5 0.61 + 0.07 3.06 1.99+ 0.06 10.17 7 0.72 + 0.004 2.58 2.21 + 0.05 8.06 9 0.75 + 0.03 2.09 2.22+ 0.06 6.03 12 0.78+ 0.04 1.63 2.25 + 0.02 4.79 14 0.89+ 0.03 1.60 2.26+ 0.07 4.12 21 0.95+ 0.12 1.14 2.31+ 0.08 2.81 30 0.97 ± 0.02 0.81 2.35 + 0.02 2.00 274 Cs-137 20% Leaching Time Activity LR x 103 Activity LR x 10 3 (d) (At, cps) 25°C (g/cmJ.d) 25°C (At, cps) 50°C (g/cm2.d) 50°C 0 Ao=2.77 + 0.02 0 Ao=2.77±0.004 0 0-11 0 0 0 0 12 0 0 0.136+ 0.001 2.139 14 0.041+ 0.004 0.053 0.139+ 0.020 1.874 21 0.050 + 0.004 0.045 0.139 ± 0.030 1.249 30 0.051 + 0.003 0.042 0.143+ 0.010 1.198 fim^ 10 eViiifminaa'Ufirmiie^am smmuemff Cs-137 ^aViiiefiwwaw'UBvimamiii 30% Leaching Time Activity LR x 103 Activity LR x 103 (d) (At, cps) 25°C (g/cmJ.d) 25°C (At, cps) 50°C (g/cm2.d) 50°C 0 Ao=22.46 + 0.01 0 Ao=22.28+0.09 0 0-11 0 0 0 0 12 0 0 0.099 + 0.005 0.168 14 0.040 + 0.006 0.058 0.152+ 0.010 0.222 21 0.053 + 0.008 0.051 0.181 + 0.020 0.176 30 0.050 + 0.005 0.045 0.201 + 0.010 0.137 11 Cs-137 viefrmenuHau'uajruefnnt 40% Leaching Time Activity LR x 10 3 Activity LR x 103 (d) (At, cps) 25°C (g/cm2.d) 25°C (At, cps) 50°C (g/cm2.d) 50°C 0 Ao=17.85±0.14 0 Ao=l 7.24+0.01 0 0-4 0 0 0 0 5 0 0 0.157 + 0.002 0.716 7 0 0 0.174 + 0.010 0.567 9 0 0 0.183+0.004 0.464 12 0 0 0.193+0.002 0.367 14 0 0 0.199 + 0.008 0.324 21 0.054+ 0.004 0.057 0.202 + 0.010 0.219 30 0.063 + 0.004 0.046 0.210 + 0.010 0.160 0.8 -LR(50oC) 0.6 -l.R<:5oC) 04 12 14 21 30 -02 0 0.2 1 2 5 7 9 12 14 21 30 Leaching Time (day) Leaching Time (day) jlifl 1 Cs-134 20 % Cs- 40 % TH9900026 ®® \_TH9900026 275 ?rmeuriitiu-90 tias tfim {kyfymnemfjmnemfja uasmfiuasmfi?? wavMu iyi 1m. 5795230 ffo 142 Twitm 5613013 -90 na ».rt. 2539-2540 f^^ tTnteuwoij-90 In UWMUJ IUW imsiiJai Sfintflu 0-3.0 0-0.2 mfiifi8i5fi/n1finfjjfff) uns; o-o.i B? 1u«i9m-3ifltnni4 fifhiilu 0.8-3.3 5aniufiifiowa/a«i 0.2-0.9 ims 0.1-0.3 mflmona/nlann>tffi Sr and Cs in Environmental Samples at Ongkharak Nuclear Research Center and Surrounding Areas Yureeporn Panyatipsakul and Pornsri Polphong Radiation Measurement Division . Office of Atomic Energy for Peace Tel. 5795230 ext. 142 Fax. 5613013 ABSTRACT Determination of Sr and Cs in environmental samples collected around Ongkharak Nuclear Research Center (ONRC) and surrounding areas during 1997-1998 were 90 obtained. Radioactivity of Sr in surface water leaf and fish were 0-3.0 mBq/1 0-0.2 Bq/kg fresh and 0-0.1 Bq/kg fresh . Radioactivity of Cs in the same samples were 0.8-3.3 mBq/1 0.2-0.9 Bq/kg fresh and 0.1-0.3 Bq/kg fresh respectively.The levels of the radioactivity show the base line levels of radioactivity at ONRC for preoperation situation which will benefit for radiation protection to the public. 276 l. umii alkaline earth group II A uasiriuiiifl0*Wniiin«jufitiMttnj flwuujeifigWumoufo «sliia"sa#uvifnsgn miiovulfuijSwaifjle'kTmJ ufllelvi'mJNtf-imym) fryneuromj-89 CST) iiastTYtteuiirtJij- 90 Csr) uri ""sr SfmutfimymnnTiw Sr mnsjjfl«in»mimfrii "sr if)utm™3»jn)u yield fioi4^n^^[-a«e ~ 3-4 % itfftaWi yiS-wm-jntiiflaej 195.8 MeV ims 0.546 MeV tfmmithumwiin 28.8 il Vt e«m1au-90 ("V) H? alkaline wSfjQjfTjJTJwyn-jtfiSluVi^mt) fl^iofl^nu group IA Sl^ lumeuioo'olmeuioo' u (soft tissue)luu^woims;^T 3 letolioiJ wSfmu^imy «ot?4in«^ou no 5WOJJ-134 (l34Cs) (136Cs) uas WMM37 (137Cs) 137Cs ii5ucn?fj9 nSfmiJ^iflqj innn-h 134Cs uas136Cs inns Si 137Cs iftutiitf i 661.6 keV l37C 90 Sr uas 137 Cs iS%4ttT3f-3^ YiSfii-mwtm iiasinwflinu^wtJttf^'wvi ivni j i.fl. 1945 yju^iii^i ™ Sr iias 137Cs 90 Sr fnimfnifmsTi'l&ia'itnil u«TlviHfi8fn?HniPiyJu5<3lu«?n -v- ufiai5tJjjDsu«nB0n«initvi50V4ift)jj scavenge m recovery yield iflomiiN'U'munfmuoiufl 2 mifrnfmeW ""Y viinfluti8g1lwtTfmsfTu faftftaj*n&tnn?flfrthieai"h-m«n imu gas flow proportional vi2 Sr nas; l37Cs y If i V • ftftau ^tmtmiiflatJUMflinvuYmYiihsinfu 316 "W flfn« 2. 2.1 l. wow (carrier) W'I-J i Re «TwifTii78Ui5t)u 10 S 20 2 50 10 wimmfln 5 2 5 2. nifnruwfli-j l&iri niwlslfi^flaoin vuf»i^u^i4 6 luaiT lias l luai? ims o.si 3. luffiriifmn «i I&iri uoulumtju Isfiionlw vuwrfu^u l Turn's uns o.i 4. tmmSoun l^iin T«»I«OJJ mfuemw uoulumwu osvmfi ijVldoi pH 5 flou lfl?uj« ivu'iiu 1.5 lutm 278 fmeW ivuvu 10 % ueaneaea 5. t1*U DOWEX 5OW-X8 (50-100 mesh) 7. IWilMfiliuleTjyil'BU^fnTiWQem-l ( stirring hot plate) 8. wntWifoed'N ( muffle furnace) 9. ^ouwiem-j (oven) 10. ifiio-aivnwwsneii (centrifuge) 11. iftte-nfii^ueaYh-iuen uuu gas flow proportional 2.2 v 2.2.1 v l. mv wTWifTYiieuwftiu fauiu 50 Saanfjj uv\z 2. mowiemaahmenifafrmi'DiuaQulutfieen «u«uimj 3.6mitimmifiin$$iv mfAs^n^rnvmu 6 Turn? 5. wnflsnoiiwieti^lw^ilDa^fniueiiiw ^ pH > 10 $wX 137Cs 6. 4,2 ('ihjflfmvliilufi'mwjnman eon 6.2 iHiwtnevi^fjQjvifjC 550 °c 6.3 tiSEntiwsineti^Qoiiin (iiumuii mvifiiinan 6.4 pH 5.5 6.5 279 6.6 asaitiflsnoufoa mfllslflsfinein flnnsnou ivle?n laflienl* w pH>9 (menifa daughter «uo^ ^Ra ivu21°Biims;2l0Poe8nflinfl'3Bm-3) 6.7 6.8 nstnowsnauflin^e 6.7 6.9 Ti^f-3^m«TUe-3 '"Y ^QfJliTlifl^^lieiiyli-tUfnimiJ gas flow proportional 7. mrjifmsiiCs-137 ammonium phosphomolybdate (AMP) frnuf 7.2 asjnt)AMP^n-3i4u^'3^'J0NH4OH mu lm^it) resin DOWEX 50W-X8 elute #10 7.3 «jjwiom-3^im«3 doafoumflluflifiuj 7.4 «nws;nou«'30m-3'lv4^iJ<«84 §ISOJJ fiaol^miwumw mm ou 7.3 Tflf^tUfl'ttie'J 137Cs ^'JOlTlQflfflSuon'Hi-mtnuiJlJ gas flow proportional 105°C 48 VQIU-3 IH1Y1 400°C y v J l. ftihwuniJiaiiJOW'JOth'JihsiJiQi 10 mu uas aTrnvrnmifawni 20 Saanfu 280 2. rioomntiwhod'ufofjmfllalfufmeinnmtf u 6 lutni feu me-wieth-j immifaK v y 3. VhlllfltrcmJlJ'lH'MUl flhUWlfo 5 2.2J iJai me wu'muniueiJfn oim 105 °c iftuntn 48 %i\w miv 400 °c iilu ny multf 3. Ti '"sr uas: wifiao-3 ihu'e 12 tfumu-a 12 wiom-a RO iliiiij v V it ihfme-a 2 MQBfli^ wiiio 3 flierin itas; ilifTis: l ^ Sr ims;137 Cs l^fil wiem3 fovttyi 5 «ie« 2 wiorn^ lu^fnSiiwtt l fliom-3 ims y ™ Sr ims; "7 Cs lll 6 vu« RO imsiJintitrn ^oiijJiD0^iJ?iJiainjjjjv4«/iiyi!'-3^ ™ Sr s B7 Cs 281 ^nw^W!/ ., _-^S=w'" ^ ^ -1^="^.-.'.-'.'. •^-^;^:-:(::>>^^:::;q^y--:•••••• 282 uas §MKJN-137 iJTU1ttAl]JUM1-m?4t}0llB(|A) &SMJ-137 y v 2.0+0.8 1.4+0.5 y y 2. 1411]!) iJeuivmitjutM <1.7 3.3±0.5 y y 3. uiiie iJ9'U'iVnqjvi&f[ 4. 1411J0 iweifni^SUIfJWI^IUoBIO (lUeM'U'HVl'U'ihflUtH) 2.6±1.1 2.7±0.5 y y 5. vinfljio^ iJ^siw?snnyviifiiiB'3utiij5svnv4 fiiio^ l 2.8±1.0 0.8±0.4 6. •U1llJJl4114m\n«fl 60M\i^7 t1UV4O-3fil'n^1Um 1.8+0.7 l.l±0.4 10. iliiwJuiufi^Tjnon Tifiijtyiuw ui>Ji4i^mn 1.4±0.8 1.2±0.4 y y 11. •uimjuiufiivnon ifm^om^ <3.3 1.3±0.4 12. iliuii'uiufiiuion QPiiJinfiiio^'wisoisnit) 1.8±0.8 1.2±0.4 283 iliuiai n u JJ ww/n-wf-J ^ flQ08"l-3UflSitflTUyuniJW19fJ1'3 (Bq/kg. fresh) fTV110UtSfJU-9O «l«WI-137 l. luyfiiBilflft WNflS'mvmthtju&'i <0.13 0.9210.04 2. nsyi 60 najw7 miuO'jfifmy^Tumuo 0.1610.03 0.6510.04 3. msmjaii-an 60 WNYI 7 ouvie^mnw^Tumvlf) <0.05 0.7610.07 4. Mtyi T?-3t1ouuTuvint)^a <0.05 0.3110.02 5. "Mtyi llTSqiS;inOl41fli18i9 O.15±O.O2 0.3910.02 7. Mtyi il'5j;g'5*intJvniitT)fnw0^pf'5 0.08±0.03 0.8210.05 ** •* rf 8. vtqji ifiijcyww ui-3ui-3mn 0.06±0.02 0.4810.03 v v <4 <0.04 0.2310.02 laAnmnm trtmmHmstmii <0.03 0.32+0.02 iJ^UItunuijUW/nnf^^ (Bq/kg.fresh) fTyi^0TilUCJJJ"9O ««mi-137 l. iJaTiJou <0.02 0.1210.02 2. iJjnqn <0.02 0.3010.02 3. llflTUfi <0.02 0.16±0.02 4. lJtntmu <0.02 0.2710.02 5. ilai«u <0.01 0.0910.01 0.0610.01 0.2610.02 284 4. uas wSeju-137 Sfhiilu 0.8-3.3 {tamimifimia/Hfli 0.2-0.9 0.1-0.3 T iS iD 5. 1. Finston HL , Kinsley NT. The radiochemistry of cesium. NAS-NC-3035 ,1961. 2. Japan Chemical Analysis Center, Japan International Cooperation Agency. Textbook for the group training course in environmental radioactivity analysis and measurement. TITC JR 93-236. 3. Kahan et al. Determination of low concentrations of radioactive cesium in water. Anal Chem 1957; 29(B): 1210-3. 4. Kathren Ronald L. Radioactivity in the environment: sources , distribution, and surveillance. New York : Harwood Academic, 1984. 5. Milintawisamai M , Panyatipsakul Y. Behaviour of Sr and Cs released into the pond of Office of Atomic Energy for Peace. Radiochimica Acta 1991 ; 54 : 155-7. 6. United Nations Scientific Committee on the Effects of Atomic Radiation. Ionizing radiation : sources and biological effects , 1982 report to the general assembly , with annexes. New York : United Nations , 1982. 7. Science and Technology Agency. Method for determination of radiostrontium. 3 rd ed. 1983. 8. m%v i?«udijD. ims'UTMiflQiuflin....g'u«u'3if)ao?im>jl qjjpli was miei arniiarfri i 2186781 1yi?(t1? 2186770 cu mu v v v ^9 (ufiJj0Pitn>in?53JiJii)?n'w?iuas;vnpiiJii4ivi 14.60 - 545.19, 7.94-20.97 tms 3.39-38.78 286 In Situ Gamma-Ray Measurement Using A High-Purity Germanium Detector Tatchai Sumitra, Nares Chankow and Paratee Sarapassorn Department of Nuclear Technology. Faculty of Engineering, Chulalongkorn University ABSTRACT Technique for in-situ gamma-ray measurement have been investigated and tested to be used for environmental gamma-ray monitoring. A portable high-purity germanium (HPGe) detector with relative efficiency of 10% was used in this research. All Calculations such as the relative detection efficiency, curve fitting, angular response correction, photon flux and so on were easily performed by using the developed formulas on the Microsoft Excel. Field gamma-ray measurements were carried out in 5 areas i.e. the field in front of Chulalongkorn University, the new site of the Nuclear Research Center in Ongkarak District of Nakornnayok Province, Banrai District of Utaitani province, Rayong Industrial Estate at Maptaput and Banpae beach of Rayong Province. The radioactivity of K, U and Th were found to be in the range of 14.6-545.2, 7.9-21.0 and 3.4-38.8 Bq/kg of soil respectively which were in good agreement with those obtained from laboratory analysis of the taken samples. 287 m m£jinii?n90i-3 IIII^I-JCT mMe^ilgiiPifniiiaiui 111 V V t r V l^i'f^ l - 2 [Nai(Ti)] (high-purity germanium, HPGe) iJ V V