SELECTED BIBLIOGRAPHY on HEAVY WATER, TRITIATED WATER and HYDROGEN ISOTOPES ( 1981-1992) by V

Total Page:16

File Type:pdf, Size:1020Kb

SELECTED BIBLIOGRAPHY on HEAVY WATER, TRITIATED WATER and HYDROGEN ISOTOPES ( 1981-1992) by V BARC/I994/E/004 CD n Hi SELECTED BIBLIOGRAPHY ON HEAVY WATER, TRITIATED WATER AND HYDROGEN ISOTOPES ( 1981-1992) by V. T. Gopalakrishnan, U. B. Sutawane and B. N. Ralhi Heavy Water Division 1994 BARC/1994/E/00* o § GOVERNMENT OF INDIA ^ ATOMIC ENERGY COMMISSION ON U < SELECTED BIBLIOGRAPHY ON HEAVY WATER, TRITIATED WATER AND HYDROGEN ISOTOPES (1981 - 1992) by V.T. Gopalakrishnan, U.B. Sutawane and B.N. Rathi Heavy Water Division BHABHA ATOMIC RESEARCH CENTRE BOMBAY, INDIA 1994 BARC/1994/E/0Q4 BIBLIOGRAPHY DESCRIPTION SHEET FOR TECHNICAL REPORT (as per IS : 9400 - 1980) 01 Security classification Unclassified 02 Distribution : External 03 Report status : New 04 Series : BARC External 05 Report type : Technical Report 06 Report No. : BARC/1994/E/OO4 07 Part No. or Volume No. : OB Contract No. : 10 Title and subtitle s Selected bibliography on heavy water, tritiated water and hydrogen isotopes (1981-1992) 11 Collation : 460 p, 13 Project No. : 20 Personal author <s) s V.T. Gopalakrishnan; U.B. Sutawane; B.N. Rathi 21 Affiliation of author (s) : Heavy Water Division, Bhabha Atomic Research Centre, Bombay 22 Corporate author<s> Bhabha Atomic Research Centre, Bombay-400 085 23 Originating unit : Heavy Water Division, BARC, Bombay 24 Sponsor(s) Name : Department of Atomic Energy Type s Government 30 Date of submission : February 1994 31 Publication/Issue date March 1994 cantd...(ii > 40 Publishtr/Distributor i Head, Library and Information Division, Bhabha Atomic Research Centre, Bombay 42 Form of distribution : Hard Copy 50 Language of text : English 51 Language of summary : English 52 No. of references : 53 Given data on : 60 Abstract : A selected bibliography on Heavy Mater, Tritiated Water and Hydrogen Isotopes is presented. This bibliography covers the period 1981 - 1992 and is in continuation to Division's earlier report BARC - 1192 (1983). The sources of information for this compilation are Chemical Abstracts, IIMIS Atomindex and also some scattered search through Journals and Reports available in our library. No claim is made towards exhaustiveness of this bibliography eventhough sincere attempts have been made for a wide coverage. The bibliography is arranged under the headings : (1) production, purification, recovery, rtporocessing and storage, (2) isotope exchange, 3) isotope analysis, (4) properties and (5) miscellaneous. Total number of references in the bibliography are 1762. 70 Keywords/Descriptors : HEAVY WATER; HYDROGEN ISOTOPES; BIBLIOGRAPHIES; ISOTOPIC EXCHANGE; ISOTOPE SEPARATION; ISOTOPE RATIO; PRODUCTION; PURIFICATION; TRITIUM OXIDES 71 Class No. : INIS Subject Category : D1200; B1210 99 Supplementary elements : PREFACE A SELECTED BIBLIOGRAPHY on Heavy Water. Tritiated Water and Hydrogen Isotopes is presented herewith. This bibliography covers the period 1981 - 1992 and is in continuation to our Division's earlier report BARC - 1192 (1983). The sources of information for this compilation are Chemical Abstracts, INIS Atomindex and also some scattered search through Journals and Reports available in our library. No claim is made towards exhaustiveness of this bibliography eventhough sincere attempts have been made for a wide coverage. We will be grateful to receive any information regarding inaccuracies that might have crept in this compilation. Last but not least, we would like to express our appreciation to the constant encouragement and helpful suggestions given to us by Shri T.G. Varadarajan, Head, Heavy Water Division and Shri H.K. Sadhukhan, Director, Chemical Engineering Group, BARC. V.T. GOPALAKRISHNAN U.B. SUTAWANE B.N. RATHI HEAVY WATER, TRIAT1ATED WATER and HYDROGEN ISOTOPES CONTENTS Page 1. SECTION I - Production, Purification, Recovery, Reprocessing and Storage 1 2. SECTION II - Isotopic exchange 165 3. SECTION III - Analysis 230 4. SECTION IV - Properties 289 5. SECTION V - Miscellaneous 340 ********** HEAVY WATER, TRITIATED WATER AND HYDROGEN ISOTOPES SECTION I PRODUCTION, PURIFICATION, RECOVERY, REPROCESSING AND STORAGE 1. Removal and recovery- of tritium from light and heavy water. J.P. Butler and M. Hammerli. Canadian Patent Document, 1093500/A/., (Int. Cl. 25 B 1/04), 13 Jan 1981. This invention relates to a method and apparatus - for removing tritium from heavy water and light water using a combined electrolysis and catalytic exchange process. 2. Finishing and upgrading of heavy water. J.P. Butler and M. Hammerli. Canadian Patent Document, 1093499/A/., (Int. 01. C 01 B 4/00), 10 pp., 13 Jan 1981. A process for deuterium enrichment for continuous on line enrichment of the heavy water in a heavy water nuclear rs-actor and for a final stage enrichment in a heavy water plant is discussed. 3. CTR fuel recovery system using regeneration of a molecular sieve drying bed. C.L. Folkers. US Patent Document, 4248607/A/, (Int. Cl. B 01 D 53/04), 3 Feb 1981. A system for the recovery of tritiated water using a primary and an auxiliary molecular sieve bed is reported. 4. Heavy water extraction from non-electrolytic hydrogen streams. R.L. LeRoy, M. Hammerli and J.P. Butler. Canadian Patent Document, 1095848/A/, (Int. Cl. C 25 E 1/00), 33., 17 Feb 1981. Heavy water production from non-electrolytic hydrogen streams using a combined electrolysis and catalytic exchange process is described. Tunable ultra-violet generator for use in the isotope separation of deuterium. E.A. Stappaerts. US Patent Document, 4254348/A/, (Int. Cl. H 03 F 7/00), 3 Mar 1961. The method presented here is suitable for heavy water production by the photodiasociation of formaldehyde in the 330-355 nm range. Process for exchanging tritium between gaseous hydrogen and water. S.G.Hindin and G.W.Roberts. UK patent document 1585556/A/., (Int.Cl.CO 165/02), BOI d 59/33, 17 pp., 4 Mar 1981. An improved method of exchanging and concentrating the rapid active isotope of hydrogen from water or hydrogen gas is described. Infrared spectrum of CTF3 and implications toward tritium isotope separation by infrared laser multiple photon dissociation of halogenated methanes. I.P. Herman and J.fi. Marling. J. Phys. Chem., 85 (5). 493-496, 5 Mar 1981. On the basis of calculated and measured absorption frequencies, photochemical separation of tritium from hydrogen is very attractive in trifluoro methane when using CO2 laser multiple photon dissociation near the strong CTF3 band centered at 1077.0 cm" and the separation of tritium from both hydrogen and deuterium is attractive when using a CO laser near the strong CTF3 band centered at 1930 cm" . Deuterium enrichment by selective photoinduced dissociation of a multihalogenated organic compound. I.P. Herman and J.B. Marling. US Patent Document, 4257860 /A/, ( Int. Cl. B 01 D 59/00 ), 7 pp., 24 March 1981. A method for deuterium enrichment by photoinduced dissociation which uses a multihalogenated organic compound as the deuterium source is described. 2 9. Tritium separation by CO2 laser multiphoton decomposition of trifluoroethane. Y. Makide and S. Hagiwara, P: 178-187. JAERI-M-9390, 279 pp., March 1981. (Japan Atomic Energy Research Inst., Tokyo. Proceedings of the U.S. / Japan workshop on fusion fuel handling. Exchange A-11 in the United States-Japan fusion cooperation program). A method for tritium separation of the CO2 laser multiphoton decomposition of trifluoroethane is studied. 10. Design study of fuel circulating system using Pd alloy membrane isotope separation method. T. Naito, T. Yamada, T. Aizawa and T. Kasahara, P: 163-177. JAERI-M-9390, 279 pp., March 1981. (Japan Atomic Energy Research Inst., Tokyo. Proceedings of the US / Japan workshop on fusion fuel handling. Exchange A-ll in the United States -Japan fusion cooperation program.) The design study of the fuel circulating system using Pd- alloy membranes is described. 11. Computer simulation study of hydrogen isotope separation system by cryogenic distillation. M. Kinoshita, P: 119-140. JAERI-M-9390, 279 pp., March 1981. ( Japan Atomic Energy Research Inst., Tokyo.) Proceedings of the US / Japan workshop on fusion fuel handling. Exchange A- 11 in the United States-Japan fusion cooperation program. This report gives a brief review of the simulation results which include those of parametric parametric investigations, examinations of effects of decay heat of tritium, Raoult's law deviation dynamics, control of the columns etc. and the outline of a computer coda system developed for the studies. 12. An assembly of tritium production experiment. T. Abe, P: 84-91. JAERI-M-9390, 279 pp., March 1981. (Japan Atomic Energy Research Inst., Tokyo. Proceedings of the US/Japan Workshop of Fusion Fuel handling. Exchange A-ll in the United States - Japan fusion cooperation program.) A small scale test facility assembly for tritium production and the preliminary results of the experiments with them are reported. 13. Rectification of heavy water prepared by electrolytic isotope concentration method. K.K. Showa Denko. Jpn. Kokai Tokkyo Koho, 8140401, ( Cl. B 01 D3/00 ), 3 pp., 16 Apr 1981. A method for obtaining heavy water of very low specific conductivity for use with rectification columns is described. KOH or NAOH is used for neutralizing acid. 14. Deuterium separation factors for isotopic exchange between hydrogen sulphide and water. S.M. Dave, S.K. Ghosh and H.K. Sadhukhan. Indian J. Chem., Sect. A., 20 (4), 329-332, Apr 1961. The overall deuterium separation factors for the hydrogen sulphide - water exchange where all the isotopic species of these molecules are in equilibrium have been calculated both for liquid-gas and gas-gas exchange as a function of temperature and deuterium concentration. IB. Procedure and equipment for the separation of isotopes for deuterium upgrading and for the production of heavy water. M. School1. DE patent document, 3118431/ A /, ( Int. Cl. B 01 D 59/36 ), 9 May 1981. A process and equipment for deuterium enrichment by oxidation of methane with bacterial cultures is described. 16. Water-hydrogen isotope exchange catalyst. K.K. Showa Denko. Jpn. Kokai Tokkyo Koho, 8156234, ( Cl. B 01 J 31/06), 6 pp., 18 May 1981.
Recommended publications
  • Tritium Handling and Safe Storage
    NOT MEASUREMENT SENSITIVE DOE-HDBK-1129-2007 March 2007 ____________________ DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1129-2007 This page is intentionally blank. ii DOE-HDBK-1129-2007 TABLE OF CONTENTS SECTION PAGE FOREWORD............................................................................................................................... vii ACRONYMS ................................................................................................................................ ix 1.0 INTRODUCTION ....................................................................................................................1 1.1 Purpose ...............................................................................................................................1 1.2 Scope ..................................................................................................................................1 1.3 Applicability .........................................................................................................................1 1.4 Referenced Material for Further Information .......................................................................2 2.0 TRITIUM .................................................................................................................................3 2.1 Radioactive Properties ........................................................................................................4
    [Show full text]
  • Tritium Immobilization and Packaging Using Metal Hydrides
    AECL-71S1 ATOMIC ENERGY flPnSy L'ENERGIE ATOMIQUE OF CANADA LIMITED V^^JP DU CANADA LIMITEE TRITIUM IMMOBILIZATION AND PACKAGING USING METAL HYDRIDES Immobilisation et emballage du tritium au moyen d'hydrures de meta! W.J. HOLTSLANDER and J.M. YARASKAVITCH Chalk River Nuclear Laboratories Laboratoires nucl6aires de Chalk River Chalk River, Ontario April 1981 avril ATOMIC ENERGY OF CANADA LIMITED Tritium Immobilization and Packaging Using Metal Hydrides by W.J. Holtslander and J.M. Yaraskavitch Chemical Engineering Branch Chalk River Nuclear Laboratories Chalk River, Ontario KOJ 1J0 1981 April AECL-7151 L'ENERGIE ATOMIQUE DU CANADA, LIMITEE Immo ;ilisation et emballage du tritium au moyen d'hydrures de mëtâT par W.J. Holtslander et J.M. Yaraskavitch Résumé Le tritium provenant des réacteurs CANDU â eau lourde devra être emballé et stocké de façon sûre. Il sera récupéré sous la forme élémentaire T2. Les tritiures de métal sont des composants efficaces pour immobiliser le tritium comme solide non réactif stable et ils peuvent en contenir beaucoup. La technologie nécessaire pour préparer les hydrures des métaux appropriés, comme le titane et le zirconium,a été développée et les propriétés des matériaux préparés ont été évaluées. La conception des emballages devant contenir les tritiures de métal, lors du transport et durant le stockage à long terme, est terminée et les premiers essais ont commencé. Département de génie chimique Laboratoires nucléaires de Chalk River Chalk River, Ontario KOJ 1J0 Avril 1981 AECL-7151 ATOMIC ENERGY OF CANADA LIMITED Tritium Immobilization and Packaging Using Metal Hydrides by W.J. Holtslander and J.M.
    [Show full text]
  • Hydrogen Is a Friend, Or an Enemy, of the Environment?
    Energy Research Journal Original Research Paper Hydrogen is a Friend, or an Enemy, of the Environment? 1Relly Victoria Virgil Petrescu, 2Raffaella Aversa, 3Taher M. Abu-Lebdeh, 2 1 Antonio Apicella and Florian Ion Tiberiu Petrescu 1ARoTMM-IFToMM, Bucharest Polytechnic University, Bucharest, (CE), Romania 2Advanced Material Lab, Department of Architecture and Industrial Design, Second University of Naples, 81031 Aversa (CE), Italy 3North Carolina A and T State University, USA Article history Abstract: Hydrogen is the best friend of man and the environment. Received: 08-02-2018 Actually, it is the core element from that can extract energy, at infinity, Revised: 15-03-2018 in various forms. Until now has not been sufficiently exploited, but Accepted: 17-03-2018 once with the evolution of the human species is the time to start to pool all types of energy which the hydrogen and its isotopes may donate Corresponding Author: Florian Ion Tiberiu Petrescu them to us. Obviously the most abundant are nuclear energies which ARoTMM-IFToMM, Bucharest may be extracted from the hydrogen, either by well-known reaction of Polytechnic University, fission or through the much-desired fusion. In the reaction of a merger Bucharest, (CE), Romania Deuterium-Tritium, for example, the energy required to overcome the E-mail: [email protected] Coulomb barrier is 0.1 MeV. Conversion between the energy and the [email protected] temperature shows that the barrier of 0.1 MeV would be exceeded at a temperature of over 1.2 billion Kelvin degrees. According to the static calculations required a temperature of fusion to warm temperature is about 4 billion degrees.
    [Show full text]
  • Tritium, Carbon-14 and Krypton-85
    Tritium, carbon-14 and krypton-85 Jan Willem Storm van Leeuwen Independent consultant member of the Nuclear Consulting Group August 2019 [email protected] Note In this document the references are coded by Q-numbers (e.g. Q6). Each reference has a unique number in this coding system, which is consistently used throughout all publications by the author. In the list at the back of the document the references are sorted by Q-number. The resulting sequence is not necessarily the same order in which the references appear in the text. m42H3C14Kr85-20190828 1 Contents 1 Introduction 2 Tritium 3H Hydrogen isotopes Anthropogenic tritium production Chemical properties DNA incorporation Health hazards Removal and disposal of tritium 3 Carbon-14 Carbon isotopes Anthropogenic carbon-14 production Chemical properties DNA incorporation Suess effect Health hazards Removal and disposal of carbon-14 4 Krypton-85 Anthropogenic kry[ton-85 production Chemical properties Biological properties Health hazards Removal and disposal of krypton-85 References TABLES Table 1 Neutron reactions producing tritium and precursors Table 2 Calculated production and discharge rates of tritium Table 3 Neutron reactions producing carbon-14 and precursors Table 4 Calculated production and discharge rates of carbon-14 Table 5 Calculated production and discharge rates of krypton-85 FIGURES Figure 1 Pathways of tritium and carbon-14 into human metabolism m42H3C14Kr85-20190828 2 1 Introduction The three radionuclides tritium (3H), carbon-14 (14C) and krypton-85 (85Kr) are routinely released into the human environment by nominally operating nuclear power plants. According to the classical dose-risk paradigm these discharges would have negligible public health effects and so were and still are permitted.
    [Show full text]
  • Chemical Names and CAS Numbers Final
    Chemical Abstract Chemical Formula Chemical Name Service (CAS) Number C3H8O 1‐propanol C4H7BrO2 2‐bromobutyric acid 80‐58‐0 GeH3COOH 2‐germaacetic acid C4H10 2‐methylpropane 75‐28‐5 C3H8O 2‐propanol 67‐63‐0 C6H10O3 4‐acetylbutyric acid 448671 C4H7BrO2 4‐bromobutyric acid 2623‐87‐2 CH3CHO acetaldehyde CH3CONH2 acetamide C8H9NO2 acetaminophen 103‐90‐2 − C2H3O2 acetate ion − CH3COO acetate ion C2H4O2 acetic acid 64‐19‐7 CH3COOH acetic acid (CH3)2CO acetone CH3COCl acetyl chloride C2H2 acetylene 74‐86‐2 HCCH acetylene C9H8O4 acetylsalicylic acid 50‐78‐2 H2C(CH)CN acrylonitrile C3H7NO2 Ala C3H7NO2 alanine 56‐41‐7 NaAlSi3O3 albite AlSb aluminium antimonide 25152‐52‐7 AlAs aluminium arsenide 22831‐42‐1 AlBO2 aluminium borate 61279‐70‐7 AlBO aluminium boron oxide 12041‐48‐4 AlBr3 aluminium bromide 7727‐15‐3 AlBr3•6H2O aluminium bromide hexahydrate 2149397 AlCl4Cs aluminium caesium tetrachloride 17992‐03‐9 AlCl3 aluminium chloride (anhydrous) 7446‐70‐0 AlCl3•6H2O aluminium chloride hexahydrate 7784‐13‐6 AlClO aluminium chloride oxide 13596‐11‐7 AlB2 aluminium diboride 12041‐50‐8 AlF2 aluminium difluoride 13569‐23‐8 AlF2O aluminium difluoride oxide 38344‐66‐0 AlB12 aluminium dodecaboride 12041‐54‐2 Al2F6 aluminium fluoride 17949‐86‐9 AlF3 aluminium fluoride 7784‐18‐1 Al(CHO2)3 aluminium formate 7360‐53‐4 1 of 75 Chemical Abstract Chemical Formula Chemical Name Service (CAS) Number Al(OH)3 aluminium hydroxide 21645‐51‐2 Al2I6 aluminium iodide 18898‐35‐6 AlI3 aluminium iodide 7784‐23‐8 AlBr aluminium monobromide 22359‐97‐3 AlCl aluminium monochloride
    [Show full text]
  • Tritiated Water Challenge in Fukushima Daiichi
    SRNL-MS-2014-00047 Tritiated water Challenge in Fukushima Daiichi Steve Xiao, Ph.D. Brian B. Looney, Ph.D. Hydrogen Processing Environmental Restoration Technology Contributions: Dave Babineau, Anita Poore Tritium Focus Group Meeting, April 2014 Fukushima Accident • Unit 1 (460 Mwe) – completely melted corium, hydrogen explosion • Unit 2 (784 Mwe) – melted, most of the radioactive releases • Unit 3 (784 Mwe) – much or all of the fuel melted, hydrogen explosion • Unit 4 (784 Mwe) – defueled prior to, damaged from Unit 3 explosion • Unit 5 (784 Mwe) – survived tsunami, to be decommissioned for training • Unit 6 (1100 Mwe) – survived tsunami, to be decommissioned for training • Currently water is circulating to cool fuels • Radioactive radionuclide removed in the loop, but not tritium • Accumulation extra 400 Ton/day due to ground water leakage • Storage of tritiated water will approach 1 million ton by 2016 Source: Fukushima Accident , World Nuclear Association, updated 22 April 2014 (http://www.world-nuclear.org/info/safety-and-security/safety-of-plants/fukushima-accident) • A treat rate of 1000 Ton/day is desired • Energy very intensive: 500 Mwe by electrolysis, 300 Mwe by distillation 2 Quarterly Video Conferences between U.S. and Japan US Decommissioning and Environmental Management Working Group • Department of State • DOE-EM • EPA • LBL • DOE IPA • PNNL • DOE-Tokyo • SRNL Japan Decommissioning and Environmental Management Working Group • METI - Japan Ministry of Economy, Trade and Industry • IRID - International Research Institute
    [Show full text]
  • Routine Releases of Tritiated Water from Nuclear Power Plants Retiring
    VOLUME 16, NUMBER 1 August 2009 AN IEER PUBLICATION Radioactive Rivers and Rain: Routine Releases of Tritiated Water From Nuclear Power Plants BY ANNIE MAKHIJANI AND ARJUN MAKHIJANI, Ph.D. uclear power plants generate tritium in the COURTESY O course of their operation and release it both to F J Nthe atmosphere and to water bodies. Tritium OE COSGROVE releases have also occurred as a result of malfunctions such as leaks (referred to by the Nuclear Regulatory Commission (NRC) as “unintended releases”) from several nuclear power plants.1 One such example of leaks was at Exelon’s Braidwood plant in Illinois. (See Figure 1.) Many reactors have experienced leaks that have not been monitored.2 Further, releases of tritiated water vapor from the stacks of nuclear power plants can result in radioactive rainfall, which can contaminate surface water bodies as well as groundwater.3 The NRC does not require monitoring of rainfall or water bodies that may be contaminated by radioactive rainfall (unless the water is otherwise required to be monitored). Figure 1. Water contaminated with tritium (up to 1,000 picocuries per liter) was found in ditches running along the west side of Center Street, a public road northeast of the Braidwood Nuclear Power Station, in March 2006. Exelon workers are seen here vacuuming the tritiated water out of the ditches. (Source: Illinois Environmental As radioactive water, tritium can Protection Agency, Exelon Braidwood Nuclear Facility: Update on Tritium Releases and Groundwater Impacts, Fact Sheet 2 (April 2006) at http://www.epa.state.il.us/ cross the placenta, posing some community-relations/fact-sheets/exelon-braidwood/exelon-braidwood-2.html) risk of birth defects and early Retiring Reference Man pregnancy failures.
    [Show full text]
  • Tritium (Hydrogen-3)
    Human Health Fact Sheet ANL, October 2001 Tritium (Hydrogen-3) What Is It? Tritium is the only radioactive isotope of hydrogen. (An Symbol: H (H-3) isotope is a different form of an element that has the same number of protons in the nucleus but a different number of neutrons.) The nucleus Atomic Number: 1 of a tritium atom consists of a proton and two neutrons. This contrasts (protons in nucleus) with the nucleus of an ordinary hydrogen atom (which consists solely of a Atomic Weight: 1 proton) and a deuterium atom (which consists of one proton and one (naturally occurring H) neutron). Ordinary hydrogen comprises over 99.9% of all naturally occurring hydrogen. Deuterium comprises about 0.02%, and tritium comprises about a billionth of a billionth (10-18) percent. The most common Radioactive Properties of Tritium forms of tritium are tritium gas Half- Natural Specific Radiation Energy (MeV) Decay (HT) and tritium Isotope Life Abundance Activity Mode Alpha Beta Gamma oxide, also called (yr) (%) (Ci/g) (α) (β) (γ) “tritiated water.” H-3 12 a trillionth 9,800 β - 0.0057 - In tritiated water, a tritium atom Ci = curie, g = gram, and MeV = million electron volts; a dash means the entry is not applicable. (See the companion fact sheet on Radioactive Properties, Internal replaces one of the Distribution, and Risk Coefficients for an explanation of terms and interpretation of hydrogen atoms so radiation energies.) Values are given to two significant figures. the chemical form is HTO rather than H2O. The chemical properties of tritium are essentially the same as those of ordinary hydrogen.
    [Show full text]
  • Evaluation of Facilities Handling Tritium Part of the Tritium Studies Project
    Canada’s Nuclear Regulator Evaluation of Facilities Handling Tritium Part of the Tritium Studies Project INFO-0796 February 2010 E VALUATION OF FACILITIES H ANDLING T RITIUM Evaluation of Facilities Handling Tritium © Minister of Public Works and Government Services Canada 2010 Catalogue number CC172-55/2010E-PDF ISBN 978-1-100-14916-5 Published by the Canadian Nuclear Safety Commission (CNSC) Catalogue number: INFO-0796 Extracts from this document may be reproduced for individual use without permission provided the source is fully acknowledged. However, reproduction in whole or in part for purposes of resale or redistribution requires prior written permission from the Canadian Nuclear Safety Commission. Également publié en français sous le titre de : Évaluation des installations de manipulation du tritium Document availability This document can be viewed on the CNSC Web site at nuclearsafety.gc.ca. To order a printed copy of the document in English or French, please contact: Canadian Nuclear Safety Commission 280 Slater Street P.O. Box 1046, Station B Ottawa, Ontario K1P 5S9 CANADA Tel.: 613-995-5894 or 1-800-668-5284 (in Canada only) Facsimile: 613-995-5086 E-mail: [email protected] Web site: nuclearsafety.gc.ca Cover images (from left to right) A bubbler monitors tritium in the air. In a tritium recovery rig, gaseous tritium light source tubes are crushed and the tritium is recovered. A filling rig is used to insert tritium into glass tubes at a gaseous tritium light source facility. A bulk splitter dispenses tritium from the commonly-used Amersham container onto smaller getter beds.
    [Show full text]
  • WO 2010/094120 Al
    (12) INTERNATIONALAPPLICATION PUBLISHED UNDER THE PATENT COOPERATION TREATY (PCT) (19) World Intellectual Property Organization International Bureau (10) International Publication Number (43) International Publication Date 26 August 2010 (26.08.2010) WO 2010/094120 Al (51) International Patent Classification: (81) Designated States (unless otherwise indicated, for every C07D 491/107 (2006.01) A61P 3/00 (2006.01) kind of national protection available): AE, AG, AL, AM, A61K 31/438 (2006.01) C07D 417/14 (2006.01) AO, AT, AU, AZ, BA, BB, BG, BH, BR, BW, BY, BZ, CA, CH, CL, CN, CO, CR, CU, CZ, DE, DK, DM, DO, (21) Number: International Application DZ, EC, EE, EG, ES, FI, GB, GD, GE, GH, GM, GT, PCT/CA20 10/0002 18 HN, HR, HU, ID, IL, IN, IS, JP, KE, KG, KM, KN, KP, (22) International Filing Date: KR, KZ, LA, LC, LK, LR, LS, LT, LU, LY, MA, MD, 16 February 2010 (16.02.2010) ME, MG, MK, MN, MW, MX, MY, MZ, NA, NG, NI, NO, NZ, OM, PE, PG, PH, PL, PT, RO, RS, RU, SC, SD, (25) Filing Language: English SE, SG, SK, SL, SM, ST, SV, SY, TH, TJ, TM, TN, TR, (26) Publication Language: English TT, TZ, UA, UG, US, UZ, VC, VN, ZA, ZM, ZW. (30) Priority Data: (84) Designated States (unless otherwise indicated, for every 61/207,784 17 February 2009 (17.02.2009) US kind of regional protection available): ARIPO (BW, GH, 61/249,284 7 October 2009 (07.10.2009) US GM, KE, LS, MW, MZ, NA, SD, SL, SZ, TZ, UG, ZM, ZW), Eurasian (AM, AZ, BY, KG, KZ, MD, RU, TJ, (71) Applicant (for all designated States except US): MER¬ TM), European (AT, BE, BG, CH, CY, CZ, DE, DK, EE, CK FROSST CANADA LTD.
    [Show full text]
  • WO 2009/126949 Al
    (12) INTERNATIONAL APPLICATION PUBLISHED UNDER THE PATENT COOPERATION TREATY (PCT) (19) World Intellectual Property Organization International Bureau (10) International Publication Number (43) International Publication Date 15 October 2009 (15.10.2009) WO 2009/126949 Al (51) International Patent Classification: (81) Designated States (unless otherwise indicated, for every A61K 31/22 (2006.01) AOlN 35/00 (2006.01) kind of national protection available): AE, AG, AL, AM, AO, AT, AU, AZ, BA, BB, BG, BH, BR, BW, BY, BZ, (21) International Application Number: CA, CH, CN, CO, CR, CU, CZ, DE, DK, DM, DO, DZ, PCT/US2009/0403 19 EC, EE, EG, ES, FI, GB, GD, GE, GH, GM, GT, HN, (22) International Filing Date: HR, HU, ID, IL, IN, IS, JP, KE, KG, KM, KN, KP, KR, 13 April 2009 (13.04.2009) KZ, LA, LC, LK, LR, LS, LT, LU, LY, MA, MD, ME, MG, MK, MN, MW, MX, MY, MZ, NA, NG, NI, NO, (25) Filing Language: English NZ, OM, PG, PH, PL, PT, RO, RS, RU, SC, SD, SE, SG, (26) Publication Language: English SK, SL, SM, ST, SV, SY, TJ, TM, TN, TR, TT, TZ, UA, UG, US, UZ, VC, VN, ZA, ZM, ZW. (30) Priority Data: 61/044,300 11 April 2008 ( 11.04.2008) US (84) Designated States (unless otherwise indicated, for every kind of regional protection available): ARIPO (BW, GH, (71) Applicant (for all designated States except US): AIDS GM, KE, LS, MW, MZ, NA, SD, SL, SZ, TZ, UG, ZM, RESEARCH ALLIANCE [US/US]; 621 -A N San Vi ZW), Eurasian (AM, AZ, BY, KG, KZ, MD, RU, TJ, cente Blvd, West Hollywood, CA 90069 (US).
    [Show full text]
  • Ca9600927 Separation of Hto from Water Using Membrane Technology
    CA9600927 SEPARATION OF HTO FROM WATER USING MEMBRANE TECHNOLOGY David A. Nelson Pacific Northwest Laboratory j Chemical Sciences Department Richland, Washington 99352 James B. Duncan Pacific Northwest Laboratory ' Waste Process Engineering Department Richland, Washington 99352 George A. Jensen Pacific Northwest Laboratory Waste Process Engineering Department Richland, Washington 99352 Sarah D. Burton Pacific Northwest Laboratory Chemical Sciences Department Richland, Washington 99352 1. ABSTRACT This research effort is being conducted to evaluate the use of membrane technology for the separation of tritium (via HTO) from sources containing HTO as a contaminant. Experience with membrane systems in industry indicates that they are inherently energy efficient. Due to the large volumes of contaminated water at U.S. Department of Energy sites, such energy efficiency would be welcome. Aromatic polyphosphazenes were chosen as the polymeric material for the membranes being investigated because they have been shown to possess excellent radiological, thermal and chemical stability We prepared poly(diphenoxy)phosphazene (PNX) and several carboxylated derivatives. Each polymer was solvent caste from dioxane onto polyethylene terephthalate support material. These composite membranes were tested with water containing 10 pCi/mL HTO under dead- end filtration conditions. The PNX provided separation (depletion) of HTO up to 36% throughout the temperature range of 2°-25°C. The 10% carboxylated PNx-membrane has shown HTO separation (depletion) up to 74% at 2°-4°C. However, little HTO depletion has been observed with this membrane at 25°C or 35°C. The membrane containing 5% carboxyl- groups appeared to present a similar depletion and temperature response. Higher carboxyl content (20% and 30%) was less efficient.
    [Show full text]