Proliferation Potential and Safeguards Challenges of Pyroprocesses
|
|
|
- Peter Owen
- 5 years ago
- Views:
Transcription
1 Proliferation Potential and Safeguards Challenges of Pyroprocesses M. Hori, S. Li, M. Pellechi International Atomic Energy Agency International Atomic Energy Agency
2 Contents Background Development of concept and technology to meet future safeguards needs of pyroprocessing facilities Proliferation potential and safeguards challenges Summary 2
3 Advanced Nuclear Fuel Cycle The nuclear industry has continued to evolve technologically in the area of advanced reactors and other advanced fuel cycle facilities With regard to recycling spent fuel, pyroprocesses have undergone a resurgence of interest in the last decade or so
4 Long Term Strategic Plan Strategy 2 Coping with the Workload Nuclear reactors and other nuclear fuel cycle facilities are designed and constructed with safeguards implementation in mind. Strategy 3 Safeguarding Advanced and Innovative Nuclear Fuel Cycles Improve preparedness to safeguard Generation III reactors, other advanced reactor types, and innovative fuel cycle facilities (Generation IV). 4
5 Long-Term R&D Plan Ability to safeguard new types of facility. 3.1 Develop generic safeguards approaches for: Pyroprocessing plants Other new reprocessing technologies Laser enrichment plants Other new enrichment technologies Small modular and/or Gen IV reactors Department of Safeguards Long-Term R&D Plan, (STR- 375) 5
6 MSSP tasks ROK C Support for Development of a Safeguards Approach for a Pyroprocessing Plant Study, Assess Field Test of Safeguards Measures and Equipment at Pyroprocessing Facilities in ROK 12/CCA-002 Implement Test, Demonstrate effective and JNT C efficient Trilateral Safeguards and Security safeguards Working Group (SSWG) under the USA/ROK Joint Fuel Cycle Study (JFCS) Document 10/CCA-005 Contribution to a Safeguards Technical Report on Pyroprocessing (EC, France, Japan, ROK) 6
7 Targets of Activities Develop effective safeguards concept and approach for the State with pyroprocessing capability Develop and demonstrate technology to improve effectiveness and efficiency Facilitate Safeguards By Design (SBD) Effective and efficient safeguards implementation No 24 hours shift inspection No On-Site Laboratory
8 Proliferation Potential Pyroprocess has lower proliferation potential compared with PUREX process Require longer time for a State to establish a production scale facility Pyroprocessing technology is under development Relevant literature is not widely available Limited capability in separating Pu, additional chemical separation activity is required for further separation of Pu Less flexibility in changing product purity and throughput High dose of U/TRU product requires additional radiation shielding Challenges include: small footprint, allow processing of spent fuels with short cooling time, essential equipment is not presently under export control
9 Safeguards Challenges Less safeguards experience Larger measurement uncertainties of feed, product, waste and in-process material, Sampling procedures, destructive analysis and non-destructive analysis for feed, product, waste and in-process materials are not yet established Process parameters are not well established Signature and indicators of the physical model need to be updated 9
10 Typical Technical Objectives Objective 1: Timely detection of the diversion of declared nuclear material Objective 2: Timely detection of the misuse of the facility to produce undeclared product from undeclared feed Objective 3: Timely detection of the misuse of the facility to produce product at Pu concentrations higher than declared, in particular relatively pure Pu 10
11 Safeguards Measures/Activities (1) Technical Objective 1: Detection of diversion Material accountancy evaluation (new type of product, sipper/receiver difference, in-process and hold-up, waste, near real time accountancy) Material accountancy verification (sampling and destructive assay, in-situ measurement, nondestructive assay) Containment and surveillance (C/S), process monitoring 11
12 Safeguards Measures/Activities (2) Technical Objective 2, 3: Detection of misuse Material accountancy, process monitoring Design information verification (DIV), other strategic point (OSP) activities (evaluation of off-normal operations and indicators), environmental sampling 12
13 Summary R&D activities related to the study and development of generic safeguards approach, test and demonstrate safeguards technologies and documentation of a technical report are being performed or planned under MSSPs Preliminary assessment of the proliferation potential of pyroprocessing technology, a study on generic technical objectives and applicable safeguards measures/activities for pyroprocessing facilities were performed Safeguards challenges to be addressed have been identified to guide the direction and focus of the R&D activities. Improve preparedness Meet future safeguards needs
14 Backup
15 Pyroprocesses and PUREX Type Process Products Effective waste disposal Effective recycle PUREX Separate U and TRU/FP U for recycle TRU/FP for disposal Separate U, U/TRU/FP, FP U for recycle U/TRU/FP for recycle FP for disposal Separate U, Pu, FP/TRU U for recycle Pu for recycle FP/TRU for disposal U ingot TRU/FP U ingot U/TRU/FP ingot FP U oxide U/Pu oxide FP/TRU (vitrified) TRU: TRans Uranium FP: Fission Product
16 Comparison of Processes U oxide PUREX Pyro Waste Disposal Decladding Decladding U separation U,Pu separation Decontamination Purification Conversion Pu Nitrate Pu separation U/Pu oxide FP/TRU (vitrified) U ingot TRU/FP Pyro Recycle Decladding U separation U/TRU separation Pu separation Pu Metal U ingot U/TRU/ FP ingot FP
17 Composition of Spent Fuel and Ingots Spent Fuel FP: 5.7% TRU: 1.4% U: 92.9% Ingot (Waste disposal) Ingot (recycle and long term storage) PWR spent fuel with 4.5 wt% initial enrichment, 10-year cooling time, and 55 GWd/MTU burn-up 85.4% of TRU is Pu
18 Comparison of Material Attractiveness Material Form and ease of processing Radiation and heat Volume Spent fuel assembly Dissolver solution U/TRU/FP ingot (Pyro waste disposal) U/TRU/FP ingot (Pyro recycle) U/Pu oxide (PUREX) Assembly/oxide Difficult Nitrate solution Easy Ingot Easy Ingot Easy Oxide powder Easy 1 1 <1 1 <1 7/ /100 2/100 1/ /100
19 Example of Frequency of Inventory Verification of Pyroprocess Product Material State without Broader Conclusion 12 U/Pu oxide (PUREX) U/Pu oxide (PUREX) State with Broader Conclusion 12 U/TRU/FP ingot (Pyro recycle) U/TRU/FP ingot (Pyro recycle) 4 U/TRU/FP ingot (Pyro waste disposal) U/TRU/FP ingot (Pyro waste disposal) Spent fuel assembly Spent fuel assembly 4 1
Advanced Fuel Cycle System R&D Activities at KAERI
IFR Symposium, Tokyo Advanced Fuel Cycle System R&D Activities at KAERI - Pyroprocessing and SFR. May 28, 2014 In-Tae Kim* Nuclear Fuel Cycle Technology Development * E-mail : nitkim@kaeri.re.kr Outline
CLOSING NUCLEAR FUEL CYCLE Prof. Myung Seung YANG Youngsan University, ROK October 19, 2016
CLOSING NUCLEAR FUEL CYCLE Prof. Myung Seung YANG Youngsan University, ROK October 19, 2016 MEET THE PRESENTER Prof. Yang graduated from the Seoul National University with a B.S. in metallurgical engineering
A Clean, Secure Nuclear Energy Solution for the 21 st Century Advanced Reactor Concepts, LLC (ARC) June 2010
A Clean, Secure Nuclear Energy Solution for the 21 st Century Advanced Reactor Concepts, LLC (ARC) June 2010 Introduction As the world grapples with the energy requirements of the future, and the associated
Status and Prospect of Safeguards By Design for Pyroprocessing Facility
0 IAEA Symposium on International Safeguards Status and Prospect of Safeguards By Design for Pyroprocessing Facility November 4, 2010 Ho-Dong KIM 1 1 2 3 4 5 Pyroprocessing Tech. Dev. Application of SBD
Transmutation of nuclear wastes by metal fuel fast reactors
PSN Number: PSNN-2014-0979 Document Number: AFT-2014-000359 Rev.000(0) Transmutation of nuclear wastes by metal fuel fast reactors International Symposium on Present Status and Future Perspective for Reducing
Advanced Fuel Cycle with Pyroprocessing and Sodium-cooled Fast Reactor in Korea
Technical Meeting on Advanced Fuel Cycles to Improve the Sustainability of Nuclear Power through the Minimization of High Level Waste, 17-19 October, 2017, Vienna, IAEA Advanced Fuel Cycle with Pyroprocessing
Introduction to the Nuclear Fuel Cycle
Introduction to the Nuclear Fuel Cycle Overview of fuel cycle Mining F R O N T E N D Milling & Extraction Convert to UF6 Enrichment Fuel Fabrication REACTOR Store U Pu LLW ILW HLW REPROCESS BACK END Store
Near-term Options for Treatment and Recyle
Near-term Options for Treatment and Recyle Dr. Alan Hanson AREVA NC Inc. Executive Vice President, Technology and Used-Fuel Management American Nuclear Society Annual Meeting June 26, 2007 Boston, MA GNEP
Advanced Non-Destructive Assay Systems and Special Instrumentation Requirements for Spent Nuclear Fuel Recycling Facilities
Advanced Non-Destructive Assay Systems and Special Instrumentation Requirements for Spent Nuclear Fuel Recycling Facilities - 8032 ABSTRACT A. P. Simpson, M. J. Clapham, B. Swinson Pajarito Scientific
Closed Fuel Cycle Strategies and National Programmes in Russia
Closed Fuel Cycle Strategies and National Programmes in Russia A.V. Bychkov RIAR, RUSSIA 9 th IEM on Actinide and Fission Products Partitioning and Transmutation Nimes, France, 25-29 September 2006 Unique
THE NUCLEAR FUEL CYCLE
THE NUCLEAR FUEL CYCLE Uranium is a slightly radioactive metal that is found throughout the earth s crust It is about 500 times more abundant than gold and about as common as tin Natural uranium is a mixture
Development of a GANEX Process
Development of a GANEX Process Emma Aneheim and Christian Ekberg Waste is what is left when imagination fails Nuclear Waste Handling The used nuclear fuel contains excess uranium, FP and trans uranic elements
Radiochemistry Webinars
National Analytical Management Program (NAMP) U.S. Department of Energy Carlsbad Field Office Radiochemistry Webinars Nuclear Fuel Cycle Series Introduction to the Nuclear Fuel Cycle In Cooperation with
Nuclear Fuel Cycle Technologies for Long-term Stable Energy Supply
Hitachi Review Vol. 58 (2009), No.2 77 Nuclear Fuel Cycle Technologies for Long-term Stable Energy Supply Tetsuo Fukasawa, Dr. Eng. Shusaku Sawada Kikuo Okada Masashi Shimizu OVERVIEW: Although the safe
The Nuclear Fuel Cycle. by B. Rouben Manager, Reactor Core Physics Branch Atomic Energy of Canada, Ltd.
The Nuclear Fuel Cycle by B. Rouben Manager, Reactor Core Physics Branch Atomic Energy of Canada, Ltd. In this seminar we ll discuss the nuclear fuel cycle: we will cover the various phases in the use
THE SODIUM-COOLED FAST REACTOR (SFR)
THE SODIUM-COOLED FAST REACTOR (SFR) M. J. Lineberry and T. R. Allen Argonne National Laboratory PO Box 2528 Idaho Falls, Id 83403-2528, U.S.A. 208-533-7760 todd.allen@anlw.anl.gov SUMMARY The Sodium-cooled
DOE Activities Promoting Understanding of Advanced Nuclear Fuel Cycles
DOE Activities Promoting Understanding of Advanced Nuclear Fuel Cycles Patricia Paviet Director for Systems Engineering and Integration (NE-51) Office of Fuel Cycle Technologies Office of Nuclear Energy
Fuel Cycle Waste Inventory
Fuel Cycle Waste Inventory Joe T. Carter and Robert H. Jones Jr. Savannah River Nuclear Solutions Actinide and Fission Product Partitioning and Transmutation 11th Information Exchange Meeting San Francisco,
Development of FBR Fuel Cycle Technology in Japan
International Conference on Fast Reactors And Related Fuel Cycles: Development of FBR Fuel Cycle Technology in Japan December 8, 2009 H. FUNASAKA, T. KOYAMA, T. NAMEKAWA and T. NAGATA Advanced Nuclear
LAS VEGAS, NV July 19-21, R. G. WYMER Vanderbilt University
OVERVIEW OF THE NUCLEAR FUEL CYCLE AND ITS CHEMISTRY SHORT COURSE : Introduction to Nuclear Chemistry and Fuel Cycle Separations LAS VEGAS, NV July 19-21, 2011 R. G. WYMER Vanderbilt University THE NUCLEAR
Neil J. Numark N.J. Numark Associates, Inc. Washington, DC. Tatsujiro Suzuki Massachusetts Institute of Technology Cambridge, MA
1993 Neil J. Numark and Tatsujiro Suzuki. All rights reserved. COMPARISON OF RECYCLE AND DISPOSAL OPTIONS FOR FISSILE MATERIALS ARISING FROM DISARMAMENT TREATIES Neil J. Numark N.J. Numark Associates,
Phase II Final Report of Feasibility Study on Commercialized Fast Reactor Cycle Systems. Executive Summary
Phase II Final Report of Feasibility Study on Commercialized Fast Reactor Cycle Systems Executive Summary March, 2006 Japan Atomic Energy Agency The Japan Atomic Power Company The Feasibility Study on
Safeguards in action: IAEA at Rokkasho, Japan
Safeguards in action: at Rokkasho, Japan Olli J. Heinonen, DDG-SG June 2010 International Atomic Energy Agency OVERVIEW of RRP Location: Aomori Prefecture, Japan Site Area: 3,800,000 m 2 Facilities: 38
Role of Partitioning and Transmutation (P&T) in Nuclear Energy
Role of Partitioning and Transmutation (P&T) in Nuclear Energy Kazufumi TSUJIMOTO Japan Atomic Energy Agency Nov. 6, 2013, Tokyo, Japan Topical Meeting embedded to INES-4 : International Nuclear Law Symposium
The Nuclear Fuel Cycle Simplified
The Nuclear Fuel Cycle Simplified Nuclear Power Committee August 27, 2009 Albert Machiels Senior Technical Executive Topics The Nuclear Fuel Cycle Simplified Light-Water Reactor (LWR) Power Block Used
Influence of Fuel Design and Reactor Operation on Spent Fuel Management
Influence of Fuel Design and Reactor Operation on Spent Fuel Management International Conference on The Management of Spent Fuel from Nuclear Power Reactors 18 June 2015 Vienna, Austria Man-Sung Yim Department
U.S. DOE currently has a number of initiatives to promote the growth of nuclear energy
U.S. Department of Energy Innovative Generation IV and Advanced Fuel Cycle Initiative Research Programs Buzz Savage AFCI Program Director U.S. DOE 1st COE-INES International Symposium Tokyo, Japan November
Modular Helium-cooled Reactor
Modular Helium-cooled Reactor The role of the GTMHR in GNEP E. Michael Campbell Francesco Venneri General Atomics April 2007 SEMA Conference 1 OUTLINE Motivation High Temperature gas reactors MHR as burner
Safeguards at research reactors: Current practices, future directions
Safeguards at research reactors: Current practices, future directions Some new verification measures are being introduced to improve the efficiency and the effectiveness of the Agency's safeguards by Giancarlo
Science of Nuclear Energy and Radiation
CNS Science of Nuclear Energy and Radiation Ben Rouben 1998 June page 1 The Nuclear Fuel Cycle Ben Rouben Manager, Reactor Core Physics AECL page 2 Topic of Discussion Nuclear fuel cycle. Will cover various
Safety of Advanced Nuclear Fuel cycles
Safety of Advanced Nuclear Fuel cycles Th. Fanghänel G. Cojazzi, N. Erdmann, D. Haas, R. Konings, V. Rondinella, J. Somers, P. van Uffelen European Commission Joint Research Centre Institute for Transuranium
Thorium an alternative nuclear fuel cycle
Thorium an alternative nuclear fuel cycle 5th Smart Grids & Clean Power Conference, Cambridge, 5 June 2013 www.cir-strategy.com/events/cleanpower Kevin Hesketh, Senior Research Fellow Outline General Principles
Nuclear Fuel Cycle Indian Scenario
Nuclear Recycle Group Nuclear Fuel Cycle Indian Scenario KAILASH AGARWAL Associate Director, NUCLEAR RECYCLE GROUP BHABHA ATOMIC RESEARCH CENTRE DEPARTMENT OF ATOMIC ENERGY MUMBAI, INDIA Advanced Fuel
Overview of long-term industry engagement with academia
Overview of long-term industry engagement with academia Professor Paul Howarth Managing Director Sept 2013 NNL Overview NNL to play a central role in HMG s Nuclear Industry Strategy announced March 2013
Safeguarding sensitive nuclear materials: Reinforced approaches
Safeguarding sensitive nuclear materials: Reinforced approaches An overview of major factors underlying the IAEA's specific approaches for safeguarding different types of sensitive nuclear materials iewed
Non-Aqueous Processes
Non-Aqueous Processes Mike Goff Idaho National Laboratory Introduction to Nuclear Fuel Cycle Chemistry July 20, 2011 Definition 1 Pyrometallurgical processing techniques involve several stages: volatilisation,
On the Practical Use of Lightbridge Thorium-based Fuels for Nuclear Power Generation
On the Practical Use of Lightbridge Thorium-based Fuels for Nuclear Power Generation Revision 1 - July 2010 Lightbridge Corporation 1600 Tysons Blvd. Suite 550 Mclean, VA 22102 USA P +1 571.730.1200 F
International safeguards aspects of spent-fuel storage
: Safeguards & non-proliferation International safeguards aspects of spent-fuel storage Techniques and approaches are evolving to meet future challenges by V. Pushkarjov and E.Tkharev Spent-fuel storage
The Integral Fast Reactor/Prism: a social & climate change perspective
The Integral Fast Reactor/Prism: a social & climate change perspective Mark Lynas Environmentalist and author, The God Species Climate change July hottest month ever in USA Arctic ice melt heading for
Fuel Recycling and MOX Production
Fuel Recycling and MOX Production Atoms for the Future Challenges of reactors and Fuel Cycle Projects Philippe KNOCHE AREVA CEO Used Nuclear Fuels Perspective and Challenges (1000 thm) LWR Used Fuel Inventories
Current options for the nuclear fuel cycle:
Current options for the nuclear fuel cycle: 1- Spent fuel disposal 2- Spent fuel reprocessing and Pu recovery Spent fuel and radiotoxicity 1/3 Composition of Spent Nuclear Fuel (Standard PWR 33GW/t, 10
The Technical Agenda for Future US-ROK Nuclear Cooperation?
The Technical Agenda for Future US-ROK Nuclear Cooperation? Ferenc Dalnoki-Veress, PhD James Martin Center for Nonproliferation Studies (CNS) Monterey Institute of International Studies, Monterey, CA July
Nuclear Power Reactors. Kaleem Ahmad
Nuclear Power Reactors Kaleem Ahmad Outline Significance of Nuclear Energy Nuclear Fission Nuclear Fuel Cycle Nuclear Power Reactors Conclusions Kaleem Ahmad, Sustainable Energy Technologies Center Key
International Atomic Energy Agency (IAEA) Activities on Spent fuel Management; Keeping the Recycle Option Open
International Atomic Energy Agency () Activities on Spent fuel Management; Keeping the Recycle Option Open Z. Lovasic WM 09 Panel on SF Recycle International Atomic Energy Agency Current world scene in
Status of Fast Reactor and Pyroprocess Technology Development in Korea
Status of Fast Reactor and Pyroprocess Technology Development in Korea International Conference on Fast Reactors and Related Fuel Cycles (FR09), Kyoto, Japan 7 December 2009 Jong-Bae CHOI 1 FR09, Kyoto,
Parametric Study of Front-End Nuclear Fuel Cycle Costs Using Reprocessed Uranium
Parametric Study of Front-End Nuclear Fuel Cycle Costs Using Reprocessed Uranium Parametric Study of Front-End Nuclear Fuel Cycle Costs Using Reprocessed Uranium 1020659 Final Report, January 2010 EPRI
Structural Changes in Nuclear Energy: Proliferation and Security Risks
Structural Changes in Nuclear Energy: Proliferation and Security Risks Sharon Squassoni Risks of Civil Use of Nuclear Energy 61 st Pugwash Conference on Science & World Affairs November 3, 2015, Nagasaki
Treatment of Spent Nuclear Fuel with Molten Salts
Treatment of Spent Nuclear Fuel with Molten Salts Michael Goff Deputy Associate Laboratory Director Operations Nuclear Science and Technology Idaho National Laboratory 2008 Joint Symposium on Molten Salts
Advanced Nuclear Fuel
Nuclear Development Advanced Nuclear Fuel Cycles and Radioactive Waste Management N U C L E A R E N E R G Y A G E N C Y Nuclear Development Advanced Nuclear Fuel Cycles and Radioactive Waste Management
Nuclear Energy Fundamentals
Nuclear Energy Fundamentals PREPARED BY Academic Services April 2012 Institute of Applied Technology, 2012 Module Objectives Upon successful completion of this module, students will be able to: Identify
Lessons learned from safeguards implementation for facilities under construction
Lessons learned from safeguards implementation for facilities under construction STEPHANIE POIRIER SAFEGUARDS EQUIPMENT IMPLEMENTATION ANALYST Fourth International Conference on Nuclear Power Plant Life
Plutonium Management in France. Current Policy and Long Term Strategy for the Used Fuel Recycling by LWR and Fast Reactors
1 Plutonium Management in France Current Policy and Long Term Strategy for the Used Fuel Recycling by LWR and Fast Reactors Christophe XERRI, Nuclear Counsellor 2 3 French Nuclear Fleet 2013 One operator:
Used Nuclear Fuel Management Options
Used Nuclear Fuel Management Options Main challenges and AREVA overall positioning November 15, 2016 Isabelle Morlaes, AREVA, Sales Back-End Dpt. SVP France & New Business Development AREVA Proprietary
Integrated Safeguards for the Plutonium Fuel Production Facility (PFPF) - Development of Approach and Applications -
Integrated Safeguards for the Plutonium Fuel Production Facility (PFPF) - Development of Approach and Applications - T. Nagatani, T. Asano, S. Fujiwara, S. Takahashi Japan Atomic Energy Agency (JAEA),
THE NUCLEAR FUEL CYCLE
Getting to the Core of THE NUCLEAR FUEL CYCLE From the mining of uranium to the disposal of nuclear waste @ Getting to the Core of the Nuclear Fuel Cycle The various activities associated with the production
Concept of Waste Management and Geological Disposal Incorporating Partitioning and Transmutation Technology
Oct. 7, 2008 10th OECD/NEA IEM on PT at Mito, Japan 1 Concept of Waste Management and Geological Disposal Incorporating Partitioning and Transmutation Technology Hiroyuki OIGAWA, Kenji NISHIHARA, Shinichi
THE FRENCH PROGRAM FOR A SUSTAINABLE MANAGEMENT OF NUCLEAR MATERIALS AND WASTE
THE FRENCH PROGRAM FOR A SUSTAINABLE MANAGEMENT OF NUCLEAR MATERIALS AND WASTE Bernard BOULLIS Fuel Cycle Back End Programs Director CEA, Nuclear Energy Division PAGE 1 International Symposium TOKYO, October
This is a repository copy of Nuclear fuel cycle: A UK perspective.
This is a repository copy of Nuclear fuel cycle: A UK perspective. White Rose Research Online URL for this paper: http://eprints.whiterose.ac.uk/97077/ Version: Presentation Conference or Workshop Item:
IAEA SAFETY STANDARDS for protecting people and the environment. Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities
DS447 Date: 20 February 2015 IAEA SAFETY STANDARDS for protecting people and the environment STATUS: SPESS STEP 12 For submission to CSS Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle
The Legacy of U.S. Energy Leadership
Future Nuclear Energy Systems: Generation IV Kevan D. Weaver, Ph.D. U.S. System Integration Manager, Gas-Cooled Fast Reactor 50th Annual Meeting of the Health Physics Society 11 July 2005 - Spokane, Washington,
Building blocks of the future fissile material (cut-off) treaty
Building blocks of the future fissile material (cut-off) treaty Pavel Podvig UN Institute for Disarmament Research UN First Committee Side Event United Nations, New York 20 October 2016 Issues to consider
Trend of Spent Fuel Management (SFM) in the World. Hojin RYU
Trend of Spent Fuel Management (SFM) in the World Tokyo, Japan 15-17 November, 2010 Hojin RYU Nuclear Fuel Cycle and Materials Section Nuclear Fuel Cycle and Spent Fuel Open Fuel Cycle Direct disposal
Perspectives of Partitioning and Transmutation Technology. H. Oigawa Japan Atomic Energy Agency
Perspectives of Partitioning and Transmutation Technology H. Oigawa Japan Atomic Energy Agency 1 Partitioning and Transmutation (P&T) Spent fuel Reprocessing FP MA U Pu MA (Np, Am, Cm) Geological disposal
Recent progress in Advanced Actinide Recycling Processes
ECD Nuclear Energy Agency 11th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation Recent progress in Advanced Actinide Recycling Processes Dominique Warin CEA /
Combined (Pyro + Hydro) technology for FR SNF reprocessing
State ГОСУДАРСТВЕННАЯ Atomic Energy Corporation КОРПОРАЦИЯ ROSATOM ПО АТОМНОЙ ЭНЕРГИИ «РОСАТОМ» Combined (Pyro + Hydro) technology for FR SNF reprocessing A.Shadrin, S. Veselov, K. Dvoeglazov, V. Volk,
Abstract ANALOGIES OF EXPERIENCE IN THE UNITED STATES TRANSURANIUM ELEMENT PRODUCTION PROGRAM
Analogies of experience in the United States Transuranium Element Production Program with partitioning and transmutation of transuranic actinides in commercial used fuels Abstract ACTINIDE AND FISSION
RECYCLING SPENT NUCLEAR FUELS FROM LWRS TO FAST REACTORS. Carole WAHIDE CEA Direction for Nuclear Energy FRANCE
RECYCLING SPENT NUCLEAR FUELS FROM LWRS TO FAST REACTORS Carole WAHIDE CEA Direction for Nuclear Energy FRANCE 1 FRENCH ELECTRICITY NUCLEAR > 75 % OF ELECTRICITY GENERATION LOW-CARBON ENERGY MIX : # 4G
Role of the Fast Reactor and Efforts on Monju
Int. Symposium on Present Status and Future Perspective for Reducing Radioactive Wastes ~ Aiming for Zero-Release~, Oct. 9-10, 2014, Tokyo Role of the Fast Reactor and Efforts on Monju October 9, 2014
Specification for Phase VII Benchmark
Specification for Phase VII Benchmark UO 2 Fuel: Study of spent fuel compositions for long-term disposal John C. Wagner and Georgeta Radulescu (ORNL, USA) November, 2008 1. Introduction The concept of
OUTLINE OF THE ROKKASHO MOX FUEL FABRICATION PLANT
OUTLINE OF THE ROKKASHO MOX FUEL FABRICATION PLANT Ikeda K., Deguchi M., Mishima T. Japan Nuclear Fuel Ltd., Rokkasho-mura, Aomori-ken 039-3212 Japan ABSTRACT: JNFL s MOX fuel fabrication plant (JMOX)
Workshop on PR&PP Evaluation Methodology for Gen IV Nuclear Energy Systems. Tokyo, Japan 22 February, Presented at
PR&PP Collaborative Study with GIF System Steering Committees A Compilation of Design Information and Crosscutting Issues Related to PR&PP Characterization Presented at Workshop on PR&PP Evaluation Methodology
FBNR Letter FIXED BED NUCLEAR REACTOR FBNR
FBNR Letter FIXED BED NUCLEAR REACTOR FBNR http://www.rcgg.ufrgs.br/fbnr.htm Farhang.Sefidvash@ufrgs.br Dear coworkers and potential coworkers around the world, As the number of coworkers is increasing,
Cooperation between AREVA and TVEL/MSZ in ERU Fuel Assembly Manufacturing - a Valuable Part of Sustainable Fuel Cycle Solutions
Cooperation between AREVA and TVEL/MSZ in ERU Fuel Assembly Manufacturing - a Valuable Part of Sustainable Fuel Cycle Solutions Ingo Koban Vice President, Mining & Front End Sales Europe & South America
May 25,
Presentation to the Blue Ribbon Commission on America s Nuclear Future Arjun Makhijani, Ph.D. President, Institute For Energy and Environmental Research Washington, DC D.C. May 25, 2010 www.ieer.org Overview
Management of the UK s plutonium stocks. Department of Energy and Climate Change
Management of the UK s plutonium stocks Department of Energy and Climate Change May 2011 Introduction The Royal Academy of Engineering responded to the Nuclear Decommissioning Authority (NDA) consultation
ICEM DEVELOPMENT OF THE ENVI SIMULATOR TO ESTIMATE KOREAN SNF FLOW AND ITS COST
Proceedings of the 12 th International Conference on Environmental Remediation And Radioactive Waste Management ICEM 2009 October 11-15, 2009, Liverpool, England, UK ICEM 2009 16060 DEVELOPMENT OF THE
Reprocessing versus Direct Disposal of Spent CANDU Nuclear Fuel: A Possible Application of Fluoride Volatility. D. Rozon and D. Lister January 2008
NWMO DISCUSSION PAPER Reprocessing versus Direct Disposal of Spent CANDU Nuclear Fuel: A Possible Application of Fluoride Volatility D. Rozon and D. Lister January 2008 (Final draft as discussed at the
RISK INFORMED SAFEGUARDS INTEGRATION STUDIES FOR A FAST REACTOR FUEL CYCLE
RISK INFORMED SAFEGUARDS INTEGRATION STUDIES FOR A FAST REACTOR FUEL CYCLE Sunil Chirayath, William Charlton, Alissa Stafford, Christopher Myers, Braden Goddard, Jeremy Alfred, Mitchell Carroll, Matthew
Nuclear power. ME922/927 Nuclear 1
Nuclear power ME922/927 Nuclear 1 The process The production of electricity by nuclear fission. Torness power station The impact of a neutron with a U 235 nucleus causes the fission process, from which
Nuclear Innovation Cooperation In the Low-Carbon Perspective
Nuclear Innovation Cooperation In the Low-Carbon Perspective NEA NI2050 Initiative Survey Process Marc Deffrennes NI2050 Workshop July 2015 Scoping paper Report WKSP Survey Questionnaire Sent out Survey
Recent achievements and remaining challenges on pyrochemical reprocessing in CRIEPI
Recent achievements and remaining challenges on pyrochemical reprocessing in CRIEPI Tsuyoshi Murakami, Koichi Uozumi, Yoshiharu Sakamura, Masatoshi Iizuka, Hirokazu Ohta, Takanari Ogata and Tadafumi Koyama
DISCLAIMER. Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.
DISCLAIMER This repod was Prepared as an accouht of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees,
OECD-NEA Task Force on Potential Benefits and Impacts of Advanced Fuel Cycles with Partitioning and Transmutation: Summary of Major Findings
OECD-NEA Task Force on Potential Benefits and Impacts of Advanced Fuel Cycles with Partitioning and Transmutation: Summary of Major Findings Massimo SALVATORES 1,2, Jan MARIVOET 3, Hiroyuki OIGAWA 4, Roald
Readiness of Current and New U.S. Reactors for MOX Fuel
Readiness of Current and New U.S. Reactors for MOX Fuel North Carolina and Virginia Health Physics Societies Joint 2009 Spring Meeting New Bern, North Carolina 13 March 2009 Andrew Sowder, Ph.D., CHP Project
WM2009 CONFERENCE Waste Management for the Nuclear Renaissance
WM2009 CONFERENCE Waste Management for the Nuclear Renaissance March 1-5 2009, Phoenix, Arizona New Policy Developments and Challenges for Radioactive Waste Management in South Africa Session 03: 10h00-12h00:
Systematic Evaluation of Uranium Utilization in Nuclear Systems
Systematic Evaluation of Uranium Utilization in Nuclear Systems Taek K. Kim and T. A. Taiwo 11 th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation San Francisco,
Current status of J-MOX safeguards design and future prospects
Current status of J-MOX safeguards design and future prospects a Tsuyoshi Sampeia, Kazuhiko Hirutaa, Junji Shimizua, Ko Ikegamea MOX Fuel Fabrication Plant Construction Office, Japan Nuclear Fuel Limited,
Safeguards and Security by Design Support for the NGNP Project
Safeguards and Security by Design Support for the NGNP Project Trond Bjornard, PhD ESARDA/INMM Joint Workshop on "Future Directions For Nuclear Safeguards and Verification" Aix-en-Provence, France October
Challenges: Global Energy Demand
Future Prospects of the Global Nuclear Partnership Jerry Paul Deputy Administrator National Nuclear Security Administration U.S. Department of Energy Presented to the Japan Atomic Energy Agency International
Effects of Repository Conditions on Environmental-Impact Reduction by Recycling
Effects of Repository Conditions on Environmental-Impact Reduction by Recycling Joonhong Ahn Department of Nuclear Engineering University of California, Berkeley OECD/NEA Tenth Information Exchange Meeting
Safeguards Obligations related to Uranium/Thorium Mining and Processing
URAM 2009, Vienna Safeguards Obligations related to Uranium/Thorium Mining and Processing Akos Petoe Division of Concepts and Planning Department of Safeguards International Atomic Energy Agency Overview
2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea
RENEWAL OF URANUM SCRAP RECOVERY FACILITES AND CAPABILITIES AT AREVA NP - RICHLAND Clifford Yeager, PE AREVA Inc., Richland Site, 2101 Horn Rapids Rd, Richland WA 99336. cliff.yeager@areva.com ABSTRACT:
COE-INES-1 CORE CONCEPT OF COMPOUND PROCESS FUEL CYCLE
COE-INES-1 CORE CONCEPT OF COMPOUND PROCESS FUEL CYCLE Objectives # Proposal of innovative nuclear fuel cycle system - economic competitiveness - efficient utilization of nuclear fuel resources - reduction
DECOMMISSIONING PROGRAMS AND TECHNOLOGY DEVELOPMENT IN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE
DECOMMISSIONING PROGRAMS AND TECHNOLOGY DEVELOPMENT IN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE Mitsugu Tanaka, Mimori Takeo, Takakuni Hirabayashi and Satoshi Yanagihara Japan Atomic Energy Research Institute
Safety Considerations in the Transition from Operation to Decommissioning of Research Reactors
Safety Considerations in the Transition from Operation to Decommissioning of Research Reactors Research Reactor Safety Section Division of Nuclear Installation Safety - EBP Workshop on the Transition Period
DRAFT IMPLEMENTING DECREE. of 2016
1. ------IND- 2016 0202 CZ- EN- ------ 20160523 --- --- PROJET II. DRAFT IMPLEMENTING DECREE of 2016 on the requirements for the safe management of radioactive waste and on the decommissioning of nuclear
Safeguard and protection requirements for Gen-IV reactor systems
Matthew Gill 25/03/13 Matthew.gill-2@postgrad.manchester.ac.uk Safeguard and protection requirements for Gen-IV reactor systems 1 Content 1. Gen-IV reactors Concepts and Advantages TRL and contribution
Practical challenges in implementing the BSS requirements (Regulatory Control of NORM): MALAYSIA. Dr. TENG IYU LIN LICENSING DIVISION
Practical challenges in implementing the BSS requirements (Regulatory Control of NORM): MALAYSIA Dr. TENG IYU LIN LICENSING DIVISION Atomic Energy Licensing Board Ministry of Science, Technology and Innovation
Laser based applications: Existing and Future Solutions
Laser based applications: Existing and Future Solutions Stephanie POIRIER International Atomic Energy Agency Department of Safeguard Division of Technical Support Surveillance Seals and Remote Monitoring.