Nuclear Production of Hydrogen, Fourth Information Exchange ...

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NUCLEAR SAFETY AND REGULATORY CONSIDERATIONS FOR NUCLEAR HYDROGEN PRODUCTION Events or releases from the nuclear plant Normal operation and some events initiated on the reactor side of the facility can impact the chemical plant and create possible pathways for the release of radioactive materials. During operation of the nuclear plant, tritium will be produced through the fission process, activation and reactions with the 3He isotope present in the coolant. Some of the tritium will migrate through the heat exchangers and make its way to the hydrogen production facility, including the hydrogen produced for subsequent use in the economy. Although the levels of tritium making their way to the hydrogen facility and commercial product may be very small, it may be necessary to evaluate the possible worker and public doses from this source and, if appropriate, establish regulatory limits. In addition to the safety and regulatory issues, the presence of minor amounts of tritium may introduce concerns in the area of public acceptance of hydrogen production using nuclear power plants. The contamination of the hydrogen facility with fission products other than tritium is less likely given the number of barriers but monitoring would likely be required as it is for possible effluents from currently operating nuclear plants. Anticipated operational occurrences and more severe transients can occur within the nuclear plant due to malfunctions of equipment, interruptions of electrical power or other initiating events. Such transients could lead to a loss of heat source to the hydrogen production or other co-generation facility and increase stresses on piping and heat exchanger tubes as a result of the changes in temperature. The NRC would review such transients to ensure that the reaction of the hydrogen production plant would not lead to a more serious challenge to the cooling of the nuclear reactor core or to a possible release of radioactive materials. A summary of issues from the NRC’s hydrogen production PIRT related to events or releases from the nuclear plant are provided in Table 3. Table 3: Summary of hydrogen PIRT chart for nuclear plant events or releases Event Evaluation criteria Issue (phenomena, process, etc.) Damage of SSC Diffusion of 3 H Anticipated operations: tritium transport (long-term safety) Dose to process gas users: Diffusion of 3 H industrial and consumers Radiological release pathways through heat exchanger loops and plant Dose to public Accidental radionuclide release Power or thermal transients initiated in nuclear reactor SSC, stress on heat exchanger or other component in contact with balance of plant Transient causes stress on SSC; induces possible transient in process facility Conclusion The NRC is currently developing the needed infrastructure and knowledge base to prepare for the licensing of the NGNP prototype and other small and medium-sized reactors. The use of high temperature gas-cooled reactors to provide process heat for hydrogen production or other chemical or petroleum facilities will introduce some additional issues for the licensing process. The NRC will build upon existing guidance for topics such as nearby chemical facilities or transportation routes in reviewing the analyses performed by applicants for nuclear plants coupled to chemical facilities. Tools such as the NGNP PIRT will identify issues, assess safety significance and define research and development needs, including the development of computer models to analyse transients and accidents, for DOE, vendors and the NRC. 360 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010
NUCLEAR SAFETY AND REGULATORY CONSIDERATIONS FOR NUCLEAR HYDROGEN PRODUCTION References Department of Energy/Nuclear Regulatory Commission (DOE/NRC) (2008), Next Generation Nuclear Plant Licensing Strategy, A Report to Congress, Joint DOE/NRC report, August. NRC (1978), Evaluation of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants, Regulatory Guide 1.91, February. NRC (2001), Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release, Regulatory Guide 1.78, December. NRC (2007), “Identification of Potential Hazards in Site Vicinity”, Section 2.2.1-2.2.2 of Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Report NUREG-0800, March. NRC (2008), “Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs)”, Process Heat and Hydrogen Co-generation PIRTs, Volume 6, Report NUREG/CR-6944, March. NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 361
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Nuclear Science 2010 Nuclear Produc
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ORGANISATION FOR ECONOMIC CO-OPERAT
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TABLE OF CONTENTS Table of contents
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TABLE OF CONTENTS Y. Gong, E. Chalk
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EXECUTIVE SUMMARY Executive summary
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EXECUTIVE SUMMARY steam turbine, in
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EXECUTIVE SUMMARY sulphur depositio
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EXECUTIVE SUMMARY affords saving 35
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EXECUTIVE SUMMARY safety assessment
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EXECUTIVE SUMMARY The question was
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CHANGING THE WORLD WITH HYDROGEN AN
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NUCLEAR HYDROGEN PRODUCTION PROGRAM
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NUCLEAR HYDROGEN PRODUCTION PROGRAM
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FRENCH RESEARCH STRATEGY TO USE NUC
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PRESENT STATUS OF HTGR AND HYDROGEN
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STATUS OF THE KOREAN NUCLEAR HYDROG
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THE CONCEPT OF NUCLEAR HYDROGEN PRO
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CANADIAN NUCLEAR HYDROGEN R&D PROGR
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APPLICATION OF NUCLEAR-PRODUCED HYD
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STATUS OF THE INL HIGH-TEMPERATURE
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HIGH-TEMPERATURE STEAM ELECTROLYSIS
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MATERIALS DEVELOPMENT FOR SOEC Mate
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A METALLIC SEAL FOR HIGH-TEMPERATUR
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DEGRADATION MECHANISMS IN SOLID OXI
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CAUSES OF DEGRADATION IN A SOLID OX
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70 μm CAUSES OF DEGRADATION IN A S
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NUCLEAR HYDROGEN USING HIGH TEMPERA
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SESSION III: THERMOCHEMICAL SULPHUR
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CEA ASSESSMENT OF THE SULPHUR-IODIN
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STATUS OF THE INERI SULPHUR-IODINE
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INFLUENCE OF HTR CORE INLET AND OUT
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EXPERIMENTAL STUDY OF THE VAPOUR-LI
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DEVELOPMENT OF HI DECOMPOSITION PRO
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SOUTH AFRICA’S NUCLEAR HYDROGEN P
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INTEGRATED LABORATORY SCALE DEMONST
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DEVELOPMENT STATUS OF THE HYBRID SU
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RECENT CANADIAN ADVANCES IN THE THE
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AN OVERVIEW OF R&D ACTIVITIES FOR T
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STUDY OF THE HYDROLYSIS REACTION OF
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DEVELOPMENT OF CuCl-HCl ELECTROLYSI
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EXERGY ANALYSIS OF THE Cu-Cl CYCLE
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CaBr 2 HYDROLYSIS FOR HBr PRODUCTIO
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SESSION V: ECONOMICS AND MARKET ANA
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DEVELOPMENT OF THE HYDROGEN ECONOMI
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NUCLEAR H 2 PRODUCTION - A UTILITY
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ALKALINE AND HIGH-TEMPERATURE ELECT
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THE PRODUCT OF HYDROGEN BY NUCLEAR
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HEAT PUMP CYCLE BY HYDROGEN-ABSORBI
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HEAT EXCHANGER TEMPERATURE RESPONSE
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ALTERNATE VHTR/HTE INTERFACE FOR MI
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POSTER SESSION CONTRIBUTIONS Poster
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ACTIVITIES OF NUCLEAR RESEARCH INST
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ACTIVITIES OF NUCLEAR RESEARCH INST
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A URANIUM THERMOCHEMICAL CYCLE FOR
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A URANIUM THERMOCHEMICAL CYCLE FOR
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MEETING ORGANISATION Annex 1: Meeti
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LIST OF PARTICIPANTS REYTIER, Magal
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LIST OF PARTICIPANTS BROWN, Nichola
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LIST OF PARTICIPANTS SINK, Carl US
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