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RECENT CANADIAN ADVANCES IN THE THERMOCHEMICAL Cu-Cl CYCLE FOR NUCLEAR HYDROGEN PRODUCTION between 450 and 550°C. This stream may contain HCl or Cl 2 gas impurities and small quantities of entrained copper oxychloride. The impurity concentrations should be small because the hydrolysis reactor (feeding the decomposition reactor) will operate at negative pressures in order to enhance the performance of the hydrolysis reactor. High Ni-Cr alloys were identified as the most promising materials of construction for this environment because of their corrosion resistance in high temperature oxidising environments. The FACTSage thermochemical database was used to identify the thermodynamically stable phases that could exist in a system comprised of a pure metal, oxygen, HCl and Cl 2 at 500°C (Suppiah, 2008). The predominant Fe, Ni, Cu and Cr phases in an O 2 /HCl/Cl 2 environment were determined. The equilibrium reaction boundary was plotted as a function of the partial pressures of O 2 and HCl, for a constant Cl 2 partial pressure. The resulting predominance diagrams were plotted over an O 2 and HCl partial pressure range of 10 –20 to 1 atm for Cl 2 partial pressures between 10 –6 and 1 atm. The predominant Ni and Cr species are solids, suggesting that a corrosion resistant protective layer could be formed on the metal. Linkage of nuclear and hydrogen plants The Generation IV nuclear reactor, Super-critical Water Reactor (SCWR) is being designed to operate at higher temperatures (550-625°C) that can facilitate co-generation of electricity and hydrogen. SCWR is expected to co-generate electricity and hydrogen uniformly throughout the year, independently of the electrical load. With an electrical load decrease, the SCWR could produce more hydrogen and vice versa. Using high temperature heat from a nuclear power plant to heat water in the hydrogen production loop is a promising option with SCWR. Heat exchangers of a recuperator-type would be used for this purpose (see Figure 2). Currently, UOIT is collaborating with AECL on various plant configurations for co-generation of electricity and hydrogen (Mokry, 2009). Figure 2: Single-reheat cycle with co-generation of hydrogen in a nuclear power plant (Mokry, 2009) Conclusions This paper has presented the recent Canadian advances in nuclear-based hydrogen production. The Cu-Cl cycle was identified by Atomic Energy of Canada Limited, AECL [Chalk River Laboratories (CRL)], as the most promising cycle for thermochemical hydrogen production with the Generation IV nuclear reactor Super-critical Water Reactor (SCWR). Recent developments of enabling technologies for the Cu-Cl cycle were presented, particularly the individual reactor designs, thermochemical properties, advanced materials and linkage between nuclear and hydrogen plants. 232 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010
RECENT CANADIAN ADVANCES IN THE THERMOCHEMICAL Cu-Cl CYCLE FOR NUCLEAR HYDROGEN PRODUCTION Acknowledgements Support of this research and assistance from Atomic Energy of Canada Limited, Ontario Research Excellence Fund, Argonne National Laboratory (International Nuclear Energy Research Initiative; US Department of Energy) and the Natural Sciences and Engineering Research Council of Canada (NSERC) are gratefully acknowledged. References Chukwu, C., G.F. Naterer, M.A. Rosen (2008), “Process Simulation of Nuclear-produced Hydrogen with a Cu-Cl Cycle”, 29 th Conference of the Canadian Nuclear Society, Toronto, Ontario, 1-4 June. Ferrandon, M.S., et al. (2008), “The Hybrid Cu-Cl Thermochemical Cycle. I. Conceptual Process Design and H2A Cost Analysis. II. Limiting the Formation of CuCl During Hydrolysis”, NHA Annual Hydrogen Conference, Sacramento Convention Center, CA, 30 March-3 April. Lewis, M., A. Taylor (2006), High Temperature Thermochemical Processes, DOE Hydrogen Program, Annual Progress Report, Washington, DC, pp. 182-185. McQuillan, B.W., et al. (2002), High Efficiency Generation of Hydrogen Fuels Using Solar Thermochemical Splitting of Water: Annual Report, GA-A24972, General Atomics, San Diego, CA. Mokry, S., et al. (2009), “Conceptual Thermal-design Options for Pressure Tube SCWRs with Thermochemical Co-generation of Hydrogen”, ASME Journal of Engineering for Gas Turbines and Power, forthcoming. Naterer, G.F., et al. (2008), “Thermochemical Hydrogen Production with a Copper-chlorine Cycle, I: Oxygen Release from Copper Oxychloride Decomposition”, International Journal of Hydrogen Energy, 33, 5439-5450. Orhan, M., I. Dincer, M.A. Rosen (2008), “Energy and Exergy Assessments of the Hydrogen Production Step of a Copper-chlorine Cycle Driven by Nuclear-based Heat”, International Journal of Hydrogen Energy, 33, 6456-6466. Sadhankar, R.R., et al. (2005), “Hydrogen Generation Using High-temperature Nuclear Reactors”, 55 th Canadian Chemical Engineering Conference, Toronto, Ontario, October. Sadhankar, R.R. (2007), “Leveraging Nuclear Research to Support the Hydrogen Economy”, International Journal of Energy Research, 31 (12), 1131-1141. Sakurai, M., et al. (2000), “Experimental Study on Side-reaction Occurrence Condition in the Iodine-sulfur Thermochemical Hydrogen Production Process”, International Journal of Hydrogen Energy, 23, 613-619. Schultz, K. (2003), Thermochemical Production of Hydrogen from Solar and Nuclear Energy, Technical Report for the Stanford Global Climate and Energy Project, General Atomics, San Diego, CA. Serban, M., M.A. Lewis, J.K. Basco (2004), “Kinetic Study of the Hydrogen and Oxygen Production Reactions in the Copper-chloride Thermochemical Cycle”, AIChE 2004 Spring National Meeting, New Orleans, LA, 25-29 April. Stevens, M.B., et al. (2008), “Macro-level Optimized Deployment of an Electrolyser-based Hydrogen Refuelling Infrastructure with Demand Growth”, Engineering Optimization, 40 (10), 955-967. NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 233
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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
Page 184 and 185: INFLUENCE OF HTR CORE INLET AND OUT
Page 194 and 195: EXPERIMENTAL STUDY OF THE VAPOUR-LI
Page 203: DEVELOPMENT OF HI DECOMPOSITION PRO
Page 206 and 207: SOUTH AFRICA’S NUCLEAR HYDROGEN P
Page 216 and 217: INTEGRATED LABORATORY SCALE DEMONST
Page 225: DEVELOPMENT STATUS OF THE HYBRID SU
Page 229 and 230: RECENT CANADIAN ADVANCES IN THE THE
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Page 237 and 238: AN OVERVIEW OF R&D ACTIVITIES FOR T
Page 245 and 246: STUDY OF THE HYDROLYSIS REACTION OF
Page 253 and 254: DEVELOPMENT OF CuCl-HCl ELECTROLYSI
Page 259: DEVELOPMENT OF CuCl-HCl ELECTROLYSI
Page 262 and 263: EXERGY ANALYSIS OF THE Cu-Cl CYCLE
Page 271 and 272: CaBr 2 HYDROLYSIS FOR HBr PRODUCTIO
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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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