Improved Core Design of High Temperature Supercritical-Pressure Light Water Reactor

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

OSTI ID:21160784

Yamaji, Akifumi; Kamei, Kazuhiro; Oka, Yoshiaki; Koshizuka, Seiichi ^[1]

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1. Nuclear Engineering Research Laboratory, Graduate School of Engineering, University of Tokyo, Tokai-Mura, Ibaraki-Prefecture, 319-1106 (Japan)

An equilibrium core of High Temperature Supercritical-Pressure Light Water Reactor is designed. Part of the feed water flows down the fuel assemblies loaded at the peripheries of the core, before flowing up the fuel channels in the inner region of the core. With this new flow scheme, the average coolant core outlet temperature is increased from 500 C of the past design to 530 C. The coolant flow rate for each fuel assembly is fixed by the inlet orifices to match the power generation. The maximum fuel rod cladding surface temperature is 650 C. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160784
• Resource Relation: Conference: ICAPP'04: 2004 international congress on advances in nuclear power plants, Pittsburgh, PA (United States), 13-17 Jun 2004; Other Information: Country of input: France; 8 refs; Related Information: In: Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04, 2338 pages.
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLADDING
COOLANTS
DESIGN
EQUILIBRIUM
FLOW RATE
FUEL ASSEMBLIES
FUEL CHANNELS
FUEL RODS
ORIFICES
POWER GENERATION
WATER
WATER COOLED REACTORS