Nuclear Production of Hydrogen, Fourth Information Exchange ...

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EXECUTIVE SUMMARY the overall efficiency of a HTGR-IS system from about 50% to 55% to justify the use of nuclear heat to produce hydrogen instead of electricity. Zr-V-F alloys were chosen because they have among the largest enthalpy changes of the hydrogen-absorbing alloys. The heat pump is incorporated into the three decomposition reactions in the cycle (H 2 SO 4 , HI and SO 3 ), in essence converting the enthalpy change of the He coolant into enthalpy changes in hydrogen production thus leading to the higher overall utilisation of the reactor heat. Richard Vilam (DOE/ANL) presented a series of papers towards mitigating structural and component failures in the heat transfer system and tritium migration between the nuclear reactor and a high-temperature electrolysis (HTE) plant for producing hydrogen through the use of control systems designed to minimise temperature differentials and more efficiently manage heat transfer and the use of ceramic materials in place of metals. In his paper titled “Heat exchanger temperature responses for duty-cycle transients in the NGNP/THE”, Vilam presented a control system for moderating the differential temperature spatial distribution in the (IHX) during duty-cycle transients. A dynamic systems simulation code was used to predict the plant response to transients such as changes in the electric generator load during normal operation and loss of load when the electrolysis plant goes off line. The study concluded that the plant load schedule could be managed to maintain near-constant temperatures over the load ranges anticipated for both the nuclear and chemical plant by use of a primary flow controller that forces flow tracked flow in the power conversion unit and a turbine bypass control for responding to step changes in the generator load. The proposed control scheme was shown to be effective in limiting temperature variations in the IHX during transients; however, it was determined that more stable operation meant operating at points on the operating curve that resulted in lower overall cycle efficiencies. In his paper titled “Alternate VHRT/THE interfaces for mitigating tritium transport and structure creep”, Vilam noted that about 90% of the heat transferred to the chemical plant is used at temperatures of below 250°C and described an alternative interface between the nuclear and chemical plants which operated at temperatures around 250°C. The small amount of high-temperature heat required by the HTE plant is obtained by using either electric heaters or hydrogen combustion. By lowering the interface operating temperature, both creep of structures and tritium migration were significantly reduced as well as structural materials and maintenance costs. Overall plant efficiency for the alternative interface design was by about 1.5% greater than that of a plant based on the conventional high-temperature interface design. Closing session Co-chairs: Yoshiyuki Nemoto (OECD/NEA), Theodore Krause (ANL) The two co-chairmen expressed their great appreciation on behalf of the Organising Committee for the interest and co-operation received from the authors, session chairman, panellists and audience. It was unfortunate that some authors were unable to participate because their request for a visa for entry into the USA could not be processed in time. David Wade (ANL) briefly described the history of this series of OECD-NEA meetings. The increasing number of papers submitted indicates a growing interest and greater awareness of the importance of the topic. The first meeting held on 2-3 October 2000 in Paris, France, had a total of 20 papers. The second meeting held on 2-3 October 2003 at Argonne, IL, USA, had 22 papers. The third meeting held on 5-7 October 2005 at Oarai, Japan, had 35 papers and the fourth meeting held on 14-16 April 2009 at Oakbrook, IL, USA, had 50 (46 oral + 4 poster) papers. It was noted that the OECD/NEA has a long history of sponsoring joint projects of many types in addition to information exchange meetings. Such projects have produced peer-reviewed databases, calculational benchmarks, and special studies – many of which were very influential. The primary objective of such joint projects is to share the costs of expensive projects and to provide access to the information gained for the participating parties. Certain areas of the research and development for the production of hydrogen from nuclear energy could be considered for such joint projects, and the participants were encouraged to contact their national representative to the NEA Science Committee if they wished to propose a project. The audience indicated that the meeting had been found to be very useful. It was suggested that in the future greater emphasis should be placed on the use of hydrogen, e.g. in the oil and chemical industries. 18 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010
EXECUTIVE SUMMARY The question was raised whether the meeting series should be continued. The meeting participants unanimously recommended that a fifth meeting should be planned by the OECD/NEA within a time frame of approximately two or two-and-a-half years. Jozef Misak, speaking on behalf of the Nuclear Research Institute-Rez (Czech Republic), indicated that his institute would be willing to serve as host if the OECD/NEA were to decide to organise and conduct a fifth meeting. If this offer is be accepted, it is proposed that the meeting be held in the beautiful and historic city of Prague. The meeting was then officially closed by OECD/NEA representative Yoshiyuki Nemoto and ANL representative Theodore Krause. NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 19
Page 1: Nuclear Science 2010 Nuclear Produc
Page 4 and 5: ORGANISATION FOR ECONOMIC CO-OPERAT
Page 7 and 8: TABLE OF CONTENTS Table of contents
Page 9 and 10: TABLE OF CONTENTS Y. Gong, E. Chalk
Page 11 and 12: EXECUTIVE SUMMARY Executive summary
Page 13 and 14: EXECUTIVE SUMMARY steam turbine, in
Page 15 and 16: EXECUTIVE SUMMARY sulphur depositio
Page 17 and 18: EXECUTIVE SUMMARY affords saving 35
Page 19: EXECUTIVE SUMMARY safety assessment
Page 24 and 25: CHANGING THE WORLD WITH HYDROGEN AN
Page 35 and 36: NUCLEAR HYDROGEN PRODUCTION PROGRAM
Page 37 and 38: NUCLEAR HYDROGEN PRODUCTION PROGRAM
Page 39 and 40: FRENCH RESEARCH STRATEGY TO USE NUC
Page 49 and 50: PRESENT STATUS OF HTGR AND HYDROGEN
Page 61 and 62: STATUS OF THE KOREAN NUCLEAR HYDROG
Page 69 and 70: THE CONCEPT OF NUCLEAR HYDROGEN PRO
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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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MARKET VIABILITY OF NUCLEAR HYDROGE
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POSSIBILITY OF ACTIVE CARBON RECYCL
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NUCLEAR SAFETY AND REGULATORY CONSI
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TRANSIENT MODELLING OF S-I CYCLE TH
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PROPOSED CHEMICAL PLANT INITIATED A
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CONCEPTUAL DESIGN OF THE HTTR-IS NU
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USE OF PSA FOR DESIGN OF EMERGENCY
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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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