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Tradeoff analysis of metal-fueled fast reactor design concepts

金属燃料高速炉設計概念のトレードオフ分析

Stauff, N. E.*; 大釜 和也; Aliberti, G.*; 大木 繁夫; Kim, T. K.*

Stauff, N. E.*; Ohgama, Kazuya; Aliberti, G.*; Oki, Shigeo; Kim, T. K.*

Within the framework of the U.S.-Japan bilateral, the Civil Nuclear Energy R&D Working Group (CNWG), a core design study was conducted by ANL and JAEA. Its objective was to compare the core performance characteristics of metal-fueled Sodium-cooled Fast Reactors (SFRs) developed with different design preferences: JAEA preferred a loop-type primary system with high coolant temperature, while ANL targeted a pool-type primary system with a conventional coolant temperature. The comparative core design study was conducted based on the 3530 MWth Japan Sodium-cooled Fast Reactor (JSFR) metallic-fuel core concept. This study confirms that both metal fueled SFR core concepts developed by ANL and JAEA based on different design preferences and approaches are viable options.

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