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PROPOSED CHEMICAL PLANT INITIATED ACCIDENT SCENARIOS IN A S-I CYCLE PLANT COUPLED TO A PEBBLE BED MODULAR REACTOR Nomenclature t F V C D A k g c P 0 D 0 Time after leak starts, seconds Fraction of initial gas weight remaining in vessel at time t Volume of the source vessel Coefficient of discharge Area of the source leak Specific heat ratio Gravitational conversion factor (for English units) Initial gas pressure Initial gas density References Bird, R.B., W.E. Stewart, E.N. Lightfoot (1960), Transport Phenomena, Wiley, New York. Brown, L.C., et al. (2003), High Efficiency Generation of Hydrogen Fuels Using Nuclear Power, Technical report, General Atomics Corp. Brown, N.R., et al. (2009), “Analysis Model for Sulfur-Iodine and Hybrid Sulfur Thermochemical Cycles”, Journal of Nuclear Technology, 166, 43-55. Reitsma, F. (2004), PBMR-268 Neutronics and Transient Benchmark Problem, PBMR Ltd., South Africa. Seker, V., T.J. Downar (2005), “Analysis of the OECD/NEA PBMR-268 Transient Benchmark Problem with the PARCS Neutronics Code”, American Nuclear Society TRANSACTIONS, 92, 697-699. 386 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010
CONCEPTUAL DESIGN OF THE HTTR-IS NUCLEAR HYDROGEN PRODUCTION SYSTEM Conceptual design of the HTTR-IS nuclear hydrogen production system: Detection of the heat transfer tube rupture in intermediate heat exchanger H. Sato, N. Sakaba, N. Sano, H. Ohashi, Y. Tachibana, K. Kunitomi Japan Atomic Energy Agency, Japan Abstract One of the key safety issues for nuclear hydrogen production is the heat transfer tube rupture in intermediated heat exchangers (IHX) which provide heat to process heat applications. This study focused on the detection method and system behaviour assessments during the IHX tube rupture scenario (IHXTR) in the HTTR coupled with IS process hydrogen production system (HTTR-IS system). The results indicate that monitoring the integral of secondary helium gas supply would be the most effective detection method. Furthermore, simultaneous actuation of two isolation valves could reduce the helium gas transportation from primary to secondary cooling systems. The results of system behaviour show that evaluation items do not exceed the acceptance criteria during the scenario. Maximum fuel temperature also does not exceed initial value and therefore the reactor core was not seriously damaged and cooled sufficiently. NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 387
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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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SUSTAINABLE ELECTRICITY SUPPLY IN T
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PROHYTEC, THE FRENCH INDUSTRIAL PLA
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NHI ECONOMIC ANALYSIS OF CANDIDATE
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Page 348 and 349: POSSIBILITY OF ACTIVE CARBON RECYCL
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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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