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Onuki, Akira; Takase, Kazuyuki; Kureta, Masatoshi; Yoshida, Hiroyuki; Tamai, Hidesada; Liu, W.; Akimoto, Hajime
Proceedings of 2004 International Congress on Advances in Nuclear Power Plants (ICAPP '04), p.1488 - 1494, 2004/06
We start R&D project to develop the predictable technology for thermal-hydraulic performance of Reduced-Moderation Water Reactor (RMWR) in collaboration with power company/reactor vendor/university since 2002. The RMWR can attain the favorable characteristics such as effective utilization of uranium resources based on matured BWR technologies. MOX fuel assemblies with tight lattice arrangement are used to increase the conversion ratio by reducing the moderation of neutron energy. Increasing the in-core void fraction also contributes to the reduction of neutron moderation. The confirmation of thermal-hydraulic feasibility is one of the most important R&D items for the RMWR. This series presentation focuses on the feasibility study and shows the R&D plan using large-scale test facility and advanced numerical simulation technology.
Sakai, Takaaki; Sakai, Takaaki; Iwasaki, Takashi*
Proceedings of 2004 International Congress on Advances in Nuclear Power Plants (ICAPP '04), p.13 - 17, 2004/06
Thermal-hydraulic analysis was performed on the Encapsulated Nuclear Heat Source (ENHS). ENHS is a Lead-Bismuth cooled natural circulation fast reactor which is designed as a candidate of Generation-IV reactor. The reactor has unique primary and secondary cooling systems flowed by natural circulation. In this study, the two-dimensional thermal-hydraulic analysis method was applied to evaluate the basic cooling performance and flow distribution in the core. Core power profile in the radial direction was considered in the calculation to discuss the inherent flow distribution caused by buoyancy force. It was clarified that beyond 10% additional flow rate is automatically distributed to the hottest channel by the inherent flow distribution. In case of a ductless-core, the additional inherent flow distribution is reduced to 5%, because of the transverse flow inside the core.
Sugino, Kazuteru; Mizuno, Tomoyasu;
Proceedings of 2004 International Congress on Advances in Nuclear Power Plants (ICAPP '04), P. 1784, 2004/06