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Nuclear Production of Hydrogen, Fourth Information Exchange ...

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CONCEPTUAL DESIGN OF THE HTTR-IS NUCLEAR HYDROGEN PRODUCTION SYSTEM<br />

References<br />

Fujikawa, S., et al., (2004), “Achievement <strong>of</strong> Reactor-outlet Coolant Temperature <strong>of</strong> 950°C in HTTR”,<br />

Journal <strong>of</strong> <strong>Nuclear</strong> Science and Technology, 41 (12), pp. 1245-1254.<br />

Kubo, S., et al. (2004), “A Demonstration Study on a Closed-cycle <strong>Hydrogen</strong> <strong>Production</strong> by the<br />

Thermochemical Water-splitting Iodine-Sulfur Process”, <strong>Nuclear</strong> Engineering and Design, 233 (1-3),<br />

pp. 347-354.<br />

Nishihara, T., et al. (1999), Conceptual Design and Selection <strong>of</strong> Deposited Material on the Valve Seat for the<br />

High Temperature Isolation Valve in the HTTR <strong>Hydrogen</strong> <strong>Production</strong> System, JAERI-Technology, 99-078.<br />

Ohashi, H., et al. (2006), “Development <strong>of</strong> Control Technology for HTTR <strong>Hydrogen</strong> <strong>Production</strong> System<br />

with Mock-up Test Facility: System Controllability Test for Loss <strong>of</strong> Chemical Reaction”, <strong>Nuclear</strong><br />

Engineering and Design, 236 (13), pp. 1396-1410.<br />

Saito, S., et al. (1994), Design <strong>of</strong> High Temperature Engineering Test Reactor (HTTR), JAERI-1332.<br />

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Water-splitting Iodine-Sulphur Process Utilizing Heat from the High-temperature Gas-cooled Reactor<br />

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Sakaba, N., et al. (2008), “Development Scenario <strong>of</strong> the Iodine-Sulphur <strong>Hydrogen</strong> <strong>Production</strong> Process to<br />

be Coupled with VHTR System as a Conventional Chemical Plant”, Journal <strong>of</strong> <strong>Nuclear</strong> Science and<br />

Technology, 45 (9), pp. 962-969.<br />

Sato, H., et al. (2007), “Conceptual Design <strong>of</strong> the HTTR-IS <strong>Hydrogen</strong> <strong>Production</strong> System – Dynamic<br />

Simulation Code Development for the Advanced Process Heat <strong>Exchange</strong>rs in the HTTR-IS system”,<br />

Proc. <strong>of</strong> International Conference on Advanced Fuel Cycles and Systems (GLOBAL2007), Boise, ID, USA,<br />

pp. 812-819.<br />

Takamatsu, K., et al. (2004), “Development <strong>of</strong> Plant Dynamics Analytical Code Named Conan-GTHTR<br />

for the Gas Turbine High Temperature Gas-cooled Reactor, (I)”, Journal <strong>of</strong> Atomic Energy Society <strong>of</strong> Japan,<br />

3 (1), pp. 76-87.<br />

Tanaka, T., et al. (1999), “Performance Test <strong>of</strong> the HTTR (High Temperature Engineering Test Reactor)”,<br />

Journal <strong>of</strong> Atomic Energy Society <strong>of</strong> Japan, 41 (6), pp. 686-696.<br />

US NRC (1995), RELAP5/MOD3 Code Manuals, Idaho National Engineering Laboratory, NUREG/CR-5535.<br />

NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 395

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