Deployment of GTHTR300 Cogeneration for Hydrogen and Electric Generation

Conference · Thu Jul 01 04:00:00 EDT 2004

OSTI ID:21160801

Kunitomi, Kazuhiko; Yan, Xing ^[1]; Minatsuki, Isao ^[2]

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1. Department of Advanced Nuclear Heat Technology, Japan Atomic Energy Research Institute, Oarai-machi, Ibaraki-ken, 311-1394 (Japan)
2. Nuclear Systems Engineering Department, Mitsubishi Heavy Industries, LTD, 3-1, Minatomirai 3-Chome, Nishi-ku, Yokohama, 220-8401 (Japan)

JAERI (Japan Atomic Energy Research Institute) has started the design study on the GTHTR300-cogeneration (GTHTR300C) aiming at producing electricity by a helium gas turbine and hydrogen by a thermochemical water splitting method (IS process method). The GTHTR300C is a block type High Temperature Gas-cooled Reactor (HTGR) with its reactor thermal power of 600 MW and outlet coolant temperature of 950 deg. C. The Intermediate Heat Exchanger (IHX) is located between the reactor pressure vessel (RPV) and the gas turbine system. The heat capacity of the IHX is 170 MW and is used for hydrogen production. The balance of the reactor thermal power is used for electric generation. The GTHTR300C is designed based on existing technologies for the High Temperature Engineering Test Reactor (HTTR) and the helium turbine power conversion technology under development for the Gas Turbine High Temperature Reactor (GTHTR300). This paper describes the deployment of the GTHTR300C together with the original design features and advantages of the system. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160801
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COGENERATION
DESIGN
GAS TURBINES
HEAT EXCHANGERS
HELIUM
HTTR REACTOR
HYDROGEN
HYDROGEN PRODUCTION
JAERI
PRESSURE VESSELS
SPECIFIC HEAT
WATER