Core and System Design of Reduced-Moderation Water Reactor with Passive Safety Features

Conference · Mon Jul 01 04:00:00 EDT 2002

OSTI ID:21167804

Iwamura, Takamichi; Okubo, Tsutomu; Yonomoto, Taisuke ^[1]; Takeda, Renzo; Moriya, Kumiaki ^[2]; Kanno, Minoru ^[3]

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1. Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195 (Japan)
2. Hitachi, Ltd. (Japan)
3. The Japan Atomic Power Company (Japan)

In order to ensure the sustainable energy supply in Japan, research and developments of reduced-moderation water reactor (RMWR) have been performed. The RMWR can attain the favorable characteristics such as high burn-up, long operation cycle, multiple recycling of plutonium and effective utilization of uranium resources, based on the matured LWR technologies. MOX fuel assemblies in the tight-lattice fuel rod arrangement are used to reduce the moderation of neutron, and hence, to increase the conversion ratio. The conceptual design has been accomplished for the small 330 MWe RMWR core with the discharge burn-up of 60 GWd/t and the operation cycle of 24 months, under the natural circulation cooling of the core. A breeding ratio of 1.01 and the negative void reactivity coefficient are simultaneously realized in the design. In the plant system design, the passive safety features are intended to be utilized mainly to improve the economy. At present, a hybrid one under the combination of the passive and the active components, and a fully passive one are proposed. The former has been evaluated to reduce the cost for the reactor components. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21167804
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BREEDING RATIO
BURNUP
COOLING
DESIGN
FUEL RODS
MIXED OXIDE FUELS
NATURAL CONVECTION
NEUTRONS
PLUTONIUM
REACTIVITY COEFFICIENTS
SAFETY
URANIUM
WATER