System Analysis for Decay Heat Removal in Lead-Bismuth Cooled Natural Circulated Reactors
- O-arai Engineering Center, Japan Nuclear Cycle Development Institute, Narita 4002, O-arai, Ibaraki, 311-1393 (Japan)
- Nuclear Energy System Inc. Narita 4002, O-arai, Ibaraki, 311-1313 (Japan)
- Advanced Reactor Technology Co. Ltd., 15-1 Tomihisa-cho, Shinjuku-ku, Tokyo, 162-0067 (Japan)
Decay heat removal analyses for lead-bismuth cooled natural circulation reactors are described in this paper. A combined multi-dimensional plant dynamics code (MSG-COPD) has been developed to conduct the system analysis for the natural circulation reactors. For the preliminary study, transient analysis has been performed for a 100 MWe lead-bismuth-cooled reactor designed by Argonne National Laboratory (ANL). In addition, decay heat removal characteristics of a 400 MWe lead-bismuth-cooled natural circulation reactor designed by Japan Nuclear Cycle Development Institute (JNC) has been evaluated by using MSG-COPD. PRACS (Primary Reactor Auxiliary Cooling System) is prepared for the JNC's concept to get sufficient heat removal capacity. During 2000 sec after the transient, the outlet temperature shows increasing tendency up to the maximum temperature of 430 Centigrade, because the buoyancy force in a primary circulation path is temporary reduced. However, the natural circulation is recovered by the PRACS system and the out let temperature decreases successfully. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21167829
- Resource Relation:
- Conference: ICAPP'02: 2002 International congress on advances in nuclear power plants, Hollywood, FL (United States), 9-13 Jun 2002; Other Information: Country of input: France; 8 refs
- Country of Publication:
- United States
- Language:
- English
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