THORIUM FUEL CYCLE DEVELOPMENT ACTIVITIES in INDIA (A Decade of Progress : 1981-1990)

Total Page:16

File Type:pdf, Size:1020Kb

THORIUM FUEL CYCLE DEVELOPMENT ACTIVITIES in INDIA (A Decade of Progress : 1981-1990) !'-i'"i, ^ ,«> '/. •': , BARC-1532 5 « to GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION THORIUM FUEL CYCLE DEVELOPMENT ACTIVITIES IN INDIA (A Decade of Progress : 1981-1990) Edited by T.K. BASU and M. SRINIVASAN December 1990 BHABHA ATOMIC RESEARCH CENTRE Bombay -400 085 BARC-1532 3 to GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION THORIUM FUEL CYCLE DEVELOPMENT ACTIVITIES IN INDIA (A Decade of Progress : 1981-1990) Edited by T.K. BASU and M. SRINIVASAN December 1990 BHABHA ATOMIC RESEARCH CENTRE Bombay -400 085 B.A.R.C.-1532 BIBLIOGRAPHIC DESCRIPTION SHEET FOR TECHNICAL REPORT (as per IS : 9400 - 1980) Ul Security classification Unclassified 02 Distribution : External 03 Report status : New 04 Series : B.A.R.C. External 05 Report type : Progress Report 06 Report No. : B.A.R.C.-1532 07 Part No. or Volume No. : 08 Contract No. : 10 Title and subtitle Thorium fuel cycle development activities an India : a decade of progress : 1981 - 1990 11 Collation : 270 p., figs., tabs. 13 Project No. : 20 Personal author(s) : T.K. Basu; M. Srinivasan (eds.) 21 Affiliation of author(s) : Neutron Physics Division, Bhabha Atomic Research Centre, Bombay 22 Corporate author(s) : Bhabha Atomic Research Centre, Bombay-400 085 23 Originating unit : Neutron Physics Division, B.A.R.C., Bocbay 24 Sponsor(s) Name : Department of Atomic Energy Type : Government 30 Date of submission : November 1990 31 Publication/Issue date December 1990 Contd... (ii) (11) 41) Pub Lisher/I)istributor : Head, Library and Information Division, Bhabha Atonic Research Centre, Bombay-400 U8J) 4'/ Korm of dist.ri but. ion : Hard oopy Language of text : Kngl ish bl Language of summary : English \y?. No. of references : rei's. 53 Gives data on : BO Abstract : The report comprises of 72 papers on various aspects of thorium fuel cycle. These papers report the research work carried out at the Bhabha Atomic Research Centre, Bombay and other units of the Department of Atomic Energy during the decade 1981-1900. 70 Keywords/Descriptors : RESEARCH PROGRAMS; INDIA; THORIUM CYCLE; NUCLKAR PURLS; THORIUM 232; FABRICATION; REPROCESSING; PHWR TYPE RKACTORS; URANIUM 233; CROSS SECTIONS; COMPUTER CODES; REACTOR PHYSICS; BREEDING; RADIATION HAZARDS 71 Class No. : INIS Subject Category : £25.00 99 Supplementary elements : PREFACE This compendium of selected papers/reports on various topics related to the technology of Thorium Fuel Cycle represents the work carried out at the Bhabha Atomic Research Centre and other units of the Department of Atomic Energy over the last decade. We are grateful to all the authors who have sent us copies of their papers. Some authors were kind enough to condense their work in the form of an extended abstract for inclusion in the present compendium. It is noted that some of the material is repeated in more than one paper but in the interest of speedy publication we have retained the original papers in the form in which they were received. This report comprises of 72 papers and is divided into ten Chapters relating to various aspects of the Thorium Fuel cycle. Although very commendable work has been done in the development of various technologies, unfortunately not many reports were readily available in a form suitable for inclusion in this report. Hence there may appear to be some imbalance in the contents of various Chapters. The number of papers in a given chapter should therefore not be taken as a true representation of the amount of work done in that particular area. However,on the whole we hope that this report would give an overview of the progress of work carried out in India in the important area of Thorium utilisation. The Editors would like to place on record their special thanks to Shri D.V. Periera for entering the manuscript into the word-processor, Dr. Anurag Shyam for help in taking the final print out and Shri S.S. Ranganekar for redrawing some of the figures from the original papers using "Publishers Paintbrush" Program. November 10, 1990 T.K. Basu, M. Srinivasan Neutron Physics Division EDITORS FOREWORD India is in a unique position with regard to nuclear fuel resources in the sense that while its natural uranium reserves are somewhat limited (70,000 tons), its thorium reserves are very large (360,000 tons). This fact was well appreciated by Homi Bhabha,. the founder of the Indian nuclear r i ogrammc-. light from its inception. It was obvious to him that in the long term India's nuclear programme would have to eventually depend on thorium. Unfortunately since thorium does not contain any fissile component, equivalent to the U-235 of natural uranium,the exploitation of fertile thorium involves -an additional step of first converting it into fissile U-233 by absorption of a neutron. It has long been recognised that this conversion can be accomplished quite efficiently in fast breeder reactors. A three stage approach was accordingly formulated to develop nuclear technology in India. But while evolving an optimum strategy for progressively incorporating thorium into the nuclear fuel cycle, considerations of achievable installed nuclear capacity growth rates under various scenarios have resulted in a continuing debate as to the most appropriate time frame in which the shift away from U-235/U-238 based fuel cycles should be effected. However, it is clear that any question of thorium entering in a significant way arises only after our natural uranium reserves are exhausted, which would happen only on completion of the first stage of our nuclear power programme comprising essentially of natural uranium fuelled PHWRs. The vast amount of plutonium that will become available from the PHWRs would be the starting point for the second stage of our programme which would involve the use of fast breeder reactors and possibly also some form of advanced or near-breeder thermal reactors. Meanwhile the progress registered in recent years in fusion and accelerator technologies has opened up prospects for direct conversion of thorium into U- 233 using one of these non fission neutron sources. This develop- ment could prepone the time table for the exploitation of thorium as an energy source in India to the earlier part of the next century. In view of the potential role of thorium in our future nuclear programme, R & D work on various aspects of the thorium fuel cycle have been underway at BARC and other units of the Department of Atomic Energy over the last three or four decades. The status of development of thorium cycle related technologies in India was reviewed earlier in two Symposia held at BARC in 1974 and 1976. The present report is a compendium of selected papers/reports describing the progress registered in this field of research during the decade of the eighties. It is being brought out on the occasion of the "Indo-Japan Seminar On Thorium Utilization" being held in Bombay during December 10th to 13th 1990. P.K. Iyengar November 10, 1990 Chairman, Atomic Energy Commission CONTENTS Page 1. FUEL CYCLE STUDIES 1. Study of alternate scenarios for the utilization of 1 thorium in advanced reactors S.M. Lee, T.M. John, P.T. Krishnakumar and S. Ganesan 2. Growth scenario with Th - HWR cycles 6 Kamala Balakrishnan and S.K. Mehta 3. Self sustaining thorium cycle in PHWR using self 10 generated plutonium Kamala Balakrishnan and S.K. Mehta 4. Self sustaining thorium cycle in HTGR 13 Kamala Balakrishnan 5. The emerging option of fusion breeders for the early 15 exploitation of thorium in the Indian context M. Srinivasan, T.K. Basu, K. Subba Rao and P.K.Iyengar 2. MINING, METALLURGY AND FUEL FABRICATION 1. A note on the new thorium plant being set up in Orissa 22 V.M. Karve 2. Thorium fuel cycle research in Fuel Chemistry Division 24 D.D. Sood 3. Development and fabrication of high density thoria 27 pellets R. Vijayaraghavan 4. Thorium Cycle-experience and development at NFC 31 K. Balaramamoorthy 5. Fabrication of aluminium clad Al-20 w/o U-233 plate 33 fuel elements for KAMINI reactor C. Ganguly 6. A high temperature study of chemical diffusion in 34 thoria - 20 mole% ceria solid solution P. Sriramamurti 7. Development of Thoria-based solid electrolyte 35 P. Sriramamurti 8. Determination of traces of rare earths in high purity 36 thorium dioxide by neutron activation analysis s.R. Kayasth, H.B. Desai and M. Sankar Das 3. LOOP EXPERIMENTS AND IRRADIATION EXPERIENCE 1. R & D on fabrication, characterisation and in-pile 38 performance of thorium fuel C. Ganguly 2. Irradiation experience with thoria based fuels 41 K. Anantharaman 3. Irradiation experience of thorium bundles in MAPS-I 43 M.V. Parikh, B. Krishna Mohan and A.N. Kumar 4. Thorium test pin ratings achievable in CIRUS-PWL 44 Umashankari P. 4. REPROCESSING 1. Laboratory studies on the recovery of Uranium-233 from 45 irradiated thorium by solvent extraction using 5% TBP shell Sol-T as solvent G.R. Balasubramaniam, R.T. Chitnis, A. Ramanujam and M. Venkatesan 2. Separation of thorium from uranium in 5% TBP on 49 amberlyst-15 M.N. Nadkarni, P.C. Mayankutty, N.S. Pillai, S.S. Shinde and S. Ravi 3. Anion exchange separation of uranium from thorium for 53 the tailend purification of U-233 in thorex process A. Mukherjee, R.T. Kulkarni, S.G. Rege, P.V. Achuthan 4. Cation exchange separation of uranium from thorium 56 R.T. Chitnis, K.G. Rajappan, S.V. Kumar, M.N. Nadkarni 5. Separation and purification of uranium product from 58 thorium in thorex process by precipitation technique A. Ramanujam, P.S. Dhami, V. Gopalakrishnan, A. Mukherjee and R.K. Dhumwad 6. Separation and purification of U-233 from boron and 65 other impurities R.T.
Recommended publications
  • Rule India Andpakistansanctionsother 15 Cfrparts742and744 Bureau Ofexportadministration Commerce Department of Part II 64321 64322 Federal Register / Vol
    Thursday November 19, 1998 Part II Department of Commerce Bureau of Export Administration 15 CFR Parts 742 and 744 India and Pakistan Sanctions and Other Measures; Interim Rule federal register 64321 64322 Federal Register / Vol. 63, No. 223 / Thursday, November 19, 1998 / Rules and Regulations DEPARTMENT OF COMMERCE Regulatory Policy Division, Bureau of missile technology reasons have been Export Administration, Department of made subject to this sanction policy Bureau of Export Administration Commerce, P.O. Box 273, Washington, because of their significance for nuclear DC 20044. Express mail address: explosive purposes and for delivery of 15 CFR Parts 742 and 744 Sharron Cook, Regulatory Policy nuclear devices. [Docket No. 98±1019261±8261±01] Division, Bureau of Export To supplement the sanctions of Administration, Department of RIN 0694±AB73 § 742.16, this rule adds certain Indian Commerce, 14th and Pennsylvania and Pakistani government, parastatal, India and Pakistan Sanctions and Avenue, NW, Room 2705, Washington, and private entities determined to be Other Measures DC 20230. involved in nuclear or missile activities FOR FURTHER INFORMATION CONTACT: to the Entity List in Supplement No. 4 AGENCY: Bureau of Export Eileen M. Albanese, Director, Office of to part 744. License requirements for Administration, Commerce. Exporter Services, Bureau of Export these entities are set forth in the newly ACTION: Interim rule. Administration, Telephone: (202) 482± added § 744.11. Exports and reexports of SUMMARY: In accordance with section 0436.
    [Show full text]
  • Vice-Chancellor‟S Report
    Vice-Chancellor‟s Report Birla Institute of Technology, Mesra, Ranchi founded by the philanthropist, industrialist Late Shri B.M. Birla in 1955, attained the status of a Deemed to be University in the year 1986. The rich legacy of the founder has been carried forward by his son Padma Bhushan Late Shri. G. P. Birla and his grandson, the present Chairman of our Board of Governors, Shri C. K. Birla through continued emphasis on academic excellence and contribution to nation building. BIT Mesra, by virtue of the quality of its academic programmes, has consistently been ranked amongst the leading technical Institutes of the country. The Institute offers academic programmes in 17 disciplines in the main Mesra campus and has 626 faculty members and over 12,000 students spread across various campuses The Institute has taken many initiatives to strengthen and expand the Teaching – Learning environment and to generate career opportunities for the students in reputed organizations. Some of these initiatives are the G P Birla Scholarship Scheme, Best Student‘s Project Award, Inter Hostel Indoor Sports Award and a strong campus placement programme. A brief report on salient activities of the Institute, undertaken during the year 2018-19 follows. 1. Board of Governors: Key decisions regarding development of the institute which were taken by the BOG are listed below. Revised UG and PG curricula conforming to Outcome-Based Education (OBE)/Choice Based Credit System (CBCS) and revised Ph.D. Ordinance have been made operational in the AY 18-19. 9 UG students participated in Immersive Summer Research Experience (ISRE) at Illinois Institute of Technology (IIT), Chicago and 3 at Carnegie Melon University (CMU) with equal sharing of expenses by BIT, BIT Mesra Alumni Association-North America (BITMAA-NA) and the participants The 7th CPC stands fully implemented.
    [Show full text]
  • P.Chellapandi, P.Puthiyavinayagam, T.Jeyakumar S.Chetal and Baldev Raj Indira Gandhi Centre for Atomic Research Kalpakkam - 603102
    P.Chellapandi, P.Puthiyavinayagam, T.Jeyakumar S.Chetal and Baldev Raj Indira Gandhi Centre for Atomic Research Kalpakkam - 603102 IAEA-Technical Meeting on ‘Design, Manufacturing and Irradiation Behavior of Fast Reactor Fuels’ 30 May-3 June 2011, IPPE, Russia Scope of Presentation Nuclear Power & FBR Programme in India Economic advantages of high burnups Int. experience on achieving high burnup Roadmap of enhancing the burnup Experience with carbide & oxide fuels Highlights of R&D Future Plans India’s Nuclear Roadmap 70000 • PHWRs from indigenous Uranium Nuclear Power Capacity • PHWRs from imported Uranium 60000 Projection (in MWe) • Imported LWR to the max. extent of 40 GW(e) 50000 • PHWRs from spent enriched U from LWRs 40000 (undersafeguard) 30000 • FBRs from reprocessed Pu and U from PHWR 20000 • FBRs from reprocessed Pu and U from LWR (undersafeguard) 10000 • U-233-Thorium Thermal / Fast Reactors 0 2010 2012 2017 2022 2032 • India has indigenous nuclear power program (4780 MW out of 20 reactors) and expects to have 20,000 MWe nuclear capacity on line by 2020 and 63,000 MWe by 2032. • Now, foreign technology and fuel are expected to boost India's nuclear power plans considerably. All plants will have high indigenous engineering content. • India has a vision of becoming a world leader in nuclear technology due to its expertise in fast reactors and thorium fuel cycle. FBR Programme in India • Indigenous Design & Construction Future FBR • Comprehensiveness in development of • 1000 MWe • Pool Type Design, R&D and Construction • Metallic fuel • High Emphasis on Scientific Breakthroughs • Serial constr. • Indegenous • Synthesis of Operating Experiences • Beyond 2025 • Synthesis of Emerging Concepts (Ex.GENIV) • Focus on National & International Weight in t No.
    [Show full text]
  • Analysis of Zirconium and Nickel Based Alloys and Zirconium Oxides
    NET318_proof ■ 22 February 2017 ■ 1/7 Nuclear Engineering and Technology xxx (2017) 1e7 Available online at ScienceDirect 65 66 1 67 2 Nuclear Engineering and Technology 68 3 69 4 70 5 journal homepage: www.elsevier.com/locate/net 71 6 72 7 73 8 74 9 Original Article 75 10 76 11 Analysis of Zirconium and Nickel Based Alloys and 77 12 78 13 Zirconium Oxides by Relative and Internal 79 14 80 15 81 16 Monostandard Neutron Activation Analysis 82 17 83 18 Q1 Methods 84 19 85 20 * 86 21 a b, a,1 Q15 Q2Amol D. Shinde , R. Acharya , and A.V.R. Reddy 87 22 88 Q3 a Analytical Chemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India 23 89 b Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India 24 90 25 91 26 92 article info abstract 27 93 28 94 29 Article history: Background: The chemical characterization of metallic alloys and oxides is conventionally 95 30 Received 9 March 2016 carried out by wet chemical analytical methods and/or instrumental methods. Instru- 96 31 Received in revised form mental neutron activation analysis (INAA) is capable of analyzing samples nondestruc- 97 32 1 August 2016 tively. As a part of a chemical quality control exercise, Zircaloys 2 and 4, nimonic alloy, and 98 33 99 34 Accepted 19 September 2016 zirconium oxide samples were analyzed by two INAA methods. The samples of alloys and Available online xxx oxides were also analyzed by inductively coupled plasma optical emission spectroscopy 100 35 101 (ICP-OES) and direct current Arc OES methods, respectively, for quality assurance pur- 36 102 Keywords: poses.
    [Show full text]
  • Separating Indian Military and Civilian Nuclear Facilities
    Separating Indian Military and Civilian Nuclear Facilities Institute for Science and International Security (ISIS) By David Albright and Susan Basu December 19, 2005 The agreement announced on July 18, 2005 by President George Bush and Prime Minister Manmohan Singh regarding the establishment of a U.S.-India “global partnership” will require changes to U.S. non-proliferation laws and policies and could dramatically increase nuclear and nuclear-related commerce with India. Part of this agreement is an Indian commitment to separate its civil and military nuclear programs and put declared civil facilities under international safeguards. Safeguards should apply in perpetuity, with minor, standard exceptions that do not include use in nuclear explosives or weapons. In addition, safeguarded nuclear material should not co-mingle with unsafeguarded nuclear material in any facility, unless this unsafeguarded nuclear material also comes under safeguards. This latter condition is an example of “contamination,” a key principle of safeguards. Although these conditions do not appear to have been accepted by India, they are necessary to prevent civil nuclear cooperation from benefiting India’s nuclear weapons program. To accomplish these goals, India needs to place all its nuclear facilities not directly associated with nuclear weapons production or deployment under safeguards. India has many civil nuclear facilities in this category. In addition, India should place its nuclear facilities associated with its naval nuclear fuel cycle under international safeguards. Exempting such naval-related facilities from safeguards would undermine efforts to safeguard such facilities in non-nuclear weapon states party to the Nuclear Non-Proliferation Treaty. Brazil accepted safeguards on its prototype naval reactor and its enrichment plants at Aramar dedicated to the production of naval reactor fuel.
    [Show full text]
  • India's Stocks of Civil and Military Plutonium and Highly Enriched Uranium, End 2014
    PlutoniumPlutonium andand HighlyHighly EnrichedEnriched UraniumUranium 20152015 INSTITUTEINSTITUTE FOR FOR SCIENCE SCIENCE AND AND INTERNATIONAL INTERNATIONAL SECURITY SECURITY India’s Stocks of Civil and Military Plutonium and Highly Enriched Uranium, End 20141 By David Albright and Serena Kelleher-Vergantini November 2, 2015 1 This report is part of a series on national and global stocks of nuclear explosive materials in both civil and military nuclear programs. This work was generously funded by a grant from the Nuclear Threat Initiative (NTI). This work builds on earlier work done at ISIS by one of the authors. 440 First Street NW, Suite 800, Washington, DC 20001 TEL 202.547.3633 Twitter @TheGoodISIS E-MAIL [email protected] • www.isis-online.org Contents Summary .............................................................................................................................................. 2 1. India’s Civil Plutonium Stockpile .................................................................................................... 3 1.1 Civil Plutonium Production ........................................................................................................ 3 1.2 Plutonium Separation ................................................................................................................. 5 1.2.1 India’s Fast Breeder Reactors .............................................................................................. 6 1.3 Unirradiated Plutonium Inventory .............................................................................................
    [Show full text]
  • Uranium Mining & Milling Industry in India
    UraniumUranium MiningMining && MillingMilling IndustryIndustry inin IndiaIndia PerPer CapitaCapita PowerPower ConsumptionConsumption 7382 7281 8000 7000 5843 6000 5000 4000 2400 3000 Energy kWh/Capita 2000 473 1000 0 Germany Japan U.K. World India Country Power:Power: TheThe urgenturgent needneed • Per capita power consumption is low. • Installed generation cap. to be raised from 138.73 to 417GWe by 2020 • Share of nuclear power to increase from 4120 to 20,000 MWe by 2020 • Uranium requirement to increase accordingly PowerPower SourcesSources andand ConstraintsConstraints COAL : •Inadequate coal reserves •Strain on transportation •High ash in Indian coal and low calorific value. • CO 2 emissions OIL & GAS AS FUEL : •Inadequate reserve, 70% requirement is met by import •Complex geo-political environment PowerPower SourcesSources andand ConstraintsConstraints HYDROELECTRIC Limited to geographically suitable sites Sites are mostly away from demand centers. Dependent on rain-fall. Effect on ecology Displacement of vast population. NON-CONVENTIONAL Limited scope at present level of technology Poor capacity factor Diffused and intermittent source “……….. We must break the constraining limits of power shortages, which retard our development. Nuclear energy is not only cost effective, it is also a cleaner alternative to fossil fuels……” Dr. Manmohan Singh, Kalapakkam, rd 23 Oct,2004 EnergyEnergy SecuritySecurity forfor IndiaIndia Non- conventional Nuclear 20% 2.0% Nuclear 2.5% Hydro 26.0% Non- conventional 7% Fossil fuels Hydro 61% Fossil fuels
    [Show full text]
  • Preparation and Submission of a Manuscript for the Proceedings
    IAEA-TM-38728 (2010) OPERATION AND UTILIZATION OF INDIAN RESEARCH REACTOR DHRUVA SAMIR KUMAR MONDAL Bhabha Atomic Research Centre, Mumbai, India [email protected] 1. INTRODUCTION The role of research reactors for the development of the nuclear programme of any country is well established. Research reactors are utilized to produce radioisotopes and offer irradiation facilities for testing various nuclear fuel and structural materials. Apart from providing a large volume neutron source for carrying out a variety of experiments, the research reactor forms the basic training facility for grooming scientists and engineers for various aspects of a nuclear programme. India’s fifth research reactor Dhruva, which became critical on 8 August 1985, is a natural uranium fuelled, heavy water moderated and cooled thermal research reactor with a rated power level of 100 MW and a maximum thermal neutron flux of 1.8×1014 cm-2s-1. The indigenously designed and built reactor is located at the Bhabha Atomic Research Centre (BARC) in Trombay. Dhruva is a product of technological initiatives taken in India during the 1970s with a totally indigenous effort when a need was felt for a research reactor having a high neutron flux to meet the growing demands of research and development. In addition, large scale production of radioisotopes with high specific activity was possible with the commissioning of Dhruva. This high flux reactor was designed and built with many innovative features which were being considered for our power reactors at that time. The reactor has a vertical core and employs natural metallic uranium in seven-pin cluster fuel assemblies installed in Zircaloy guide tubes in a stainless steel reactor vessel.
    [Show full text]
  • Professor Jaikrishna and Professor Sn Mitra Memorial Award Lectures
    PROFESSOR JAIKRISHNA AND PROFESSOR S.N. MITRA MEMORIAL AWARD LECTURES INDIAN NATIONAL ACADEMY OF ENGINEERING April 2018 INDIAN NATIONAL ACADEMY OF ENGINEERING GOVERNING COUNCIL Office Bearers President Dr. B.N. Suresh Vice-Presidents Dr. Indranil Manna Dr. Pumendu Ghosh Dr. Pradip Chief Editor of Publications Dr. Pumendu Ghosh Executive Director Brig RajanMinocha The Indian National Academy of Engineering (INAE) is an autonomous institution partly supported by the Department of Science and Technology, Govt, of India and is recognized as a Scientific and Industrial Research Organization (SIRO) by the Department of Scientific and Industrial Research, Govt, of India. Registered Office Indian National Academy of Engineering Unit No. 604-609, SPAZE, I Tech Park, 6th Floor, Tower A, Sector 49, Sohna Road Gurgaon - 122 002 (India) Phone: (91) - 0124 - 4239480 Fax: (91)-0124-4239481 Email: [email protected] Website: www.inae.in © Copyright 2018. Indian National Academy of Engineering. All rights reserved Published by the Indian National Academy of Engineering, New Delhi Printed at the Naman Stickers, 96-B, 4 D Campus, Murlipura, Jaipur PROFESSOR JAIKRISHNA AND PROFESSOR S.N. MITRA MEMORIAL AWARD LECTURES INDIAN NATIONAL ACADEMY OF ENGINEERING April 2018 Award Lecture Series of Indian National Academy of Engineering EDITORIAL The Indian National Academy of Engineering (INAE) functions as an apex body that promotes the practice of engineering and technology in solving problems of national importance. Its activities include formulation of technology policies, promotion of quality engineering education, and encouraging R&D activities. With an objective to promote engineering excellence INAE has instituted Professor Jai Krishna and Professor S N Mitra memorial awards.
    [Show full text]
  • Nuclear Engineering and Technology 49 (2017) 562E568
    Nuclear Engineering and Technology 49 (2017) 562e568 Available online at ScienceDirect Nuclear Engineering and Technology journal homepage: www.elsevier.com/locate/net Original Article Analysis of Zirconium and Nickel Based Alloys and Zirconium Oxides by Relative and Internal Monostandard Neutron Activation Analysis Methods * Amol D. Shinde a, Raghunath Acharya b, , and Annareddy V.R. Reddy a a Analytical Chemistry Division, Mod Labs, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India b Radiochemistry Division, Radiological Laboratories, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India article info abstract Article history: Background: The chemical characterization of metallic alloys and oxides is conventionally Received 9 March 2016 carried out by wet chemical analytical methods and/or instrumental methods. Instru- Received in revised form mental neutron activation analysis (INAA) is capable of analyzing samples nondestruc- 1 August 2016 tively. As a part of a chemical quality control exercise, Zircaloys 2 and 4, nimonic alloy, and Accepted 19 September 2016 zirconium oxide samples were analyzed by two INAA methods. The samples of alloys and Available online 6 February 2017 oxides were also analyzed by inductively coupled plasma optical emission spectroscopy (ICP-OES) and direct current Arc OES methods, respectively, for quality assurance pur- Keywords: poses. The samples are important in various fields including nuclear technology. AES Methods: Samples were neutron irradiated using nuclear reactors, and the radioactive assay Chemical Quality Control was carried out using high-resolution gamma-ray spectrometry. Major to trace mass IM-NAA fractions were determined using both relative and internal monostandard (IM) NAA INAA methods as well as OES methods.
    [Show full text]
  • Global Fissile Material Report 2015 Nuclear Weapon and Fissile Material Stockpiles and Production
    Global Fissile Material Report 2015 Nuclear Weapon and Fissile Material Stockpiles and Production Eighth annual report of the International Panel on Fissile Materials Eighth annual report of the International Panel on Fissile Materials Global Fissile Material Report 2015 Nuclear Weapon and Fissile Material Stockpiles and Production 2015 International Panel on Fissile Materials This work is licensed under the Creative Commons Attribution-Noncommercial License To view a copy of this license, visit www.creativecommons.org/licenses/by-nc/3.0 On the cover: the map shows existing uranium enrichment and plutonium separation (reprocessing) facilities. Table of Contents About the IPFM 1 Summary 2 Nuclear Weapons 4 Highly Enriched Uranium 10 Military HEU 13 Civilian Use of HEU 17 Civilian Uranium Enrichment Plants 19 Separated Plutonium 23 Weapons Plutonium 25 Civilian Plutonium 29 Nuclear Weapons, Fissile Materials and Transparency 34 Appendix 1. Fissile Materials and Nuclear Weapons 40 Appendix 2. Uranium Enrichment Plants 48 Appendix 3. Reprocessing Plants 49 Appendix 4. Civilian Plutonium Stockpile Declarations 50 Endnotes 51 About the IPFM The International Panel on Fissile Materials (IPFM) was founded in January 2006. It is an independent group of arms-control and nonproliferation experts from seventeen countries, including both nuclear weapon and non-nuclear weapon states. The mission of the IPFM is to analyze the technical basis for practical and achievable policy initiatives to secure, consolidate, and reduce stockpiles of highly enriched urani- um and plutonium. These fissile materials are the key ingredients in nuclear weapons, and their control is critical to nuclear disarmament, halting the proliferation of nuclear weapons, and ensuring that terrorists do not acquire nuclear weapons.
    [Show full text]
  • TRANSITION from OPERATION to DECOMMISSIONING of CIRUS RESEARCH REACTOR by Rakesh Ranjan, S
    BARC/2018/E/005 BARC/2018/E/005 TRANSITION FROM OPERATION TO DECOMMISSIONING OF CIRUS RESEARCH REACTOR by Rakesh Ranjan, S. Bhattacharya, C.G . Karhadkar, Prasit Mandal, M.K. Ojha Reactor Operations Division 2018 BARC/2018/E/005 GOVERNMENT OF INDIA DEPARTMENT OF ATOMIC ENERGY BARC/2018/E/005 TRANSITION FROM OPERATION TO DECOMMISSIONING OF CIRUS RESEARCH REACTOR by Rakesh Ranjan*, S. Bhattacharya, C.G . Karhadkar, Prasit Mandal, M.K. Ojha [email protected]* Reactor Operations Division Reactor Group BHABHA ATOMIC RESEARCH CENTRE MUMBAI, INDIA 2018 BARC/2018/E/005 BIBLIOGRAPHIC 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/2018/E/005 07 Part No. or Volume No. : 08 Contract No. : 10 Title and subtitle : Transition from operation to decommissioning of Cirus research reactor 11 Collation : 82 p., 39 figs., 9 tabs. 13 Project No. : 20 Personal author(s) : Rakesh Ranjan; S. Bhattacharya, C.G. Karhadkar; Prasit Mandal; M.K. Ojha 21 Affiliation of author(s) : Reactor Operations Division, Bhabha Atomic Research Centre, Mumbai 22 Corporate author(s): Bhabha Atomic Research Centre, Mumbai - 400 085 23 Originating unit : Reactor Operations Division, Bhabha Atomic Research Centre, Mumbai 24 Sponsor(s) Name : Department of Atomic Energy Type : Government Contd... BARC/2018/E/005 30 Date of submission : April 2018 31 Publication/Issue date : April 2018 40 Publisher/Distributor : Head, Scientific Information Resource Division, Bhabha Atomic Research Centre, Mumbai 42 Form of distribution : Hard copy 50 Language of text : English 51 Language of summary : English 52 No.
    [Show full text]