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Design study of a 750 MWe Japan sodium-cooled fast reactor with metal fuel

750MWeのナトリウム冷却金属燃料高速炉の設計研究

大釜 和也; 太田 宏一*; 生澤 佳久; 大木 繁夫; 尾形 孝成*

Ohgama, Kazuya; Ota, Hirokazu*; Ikusawa, Yoshihisa; Oki, Shigeo; Ogata, Takanari*

Under the collaborative research of Central Research Institute of Electric Power Industry (CRIEPI) and Japan Atomic Energy Agency (JAEA), the metal fuel core concept has been studied. In this study, a 750 MWe sodium-cooled fast reactor (SFR) with metal fuel designed in a past/precedent study was reevaluated considering the irradiation behaviors of metal fuel such as axial elongation and bond-sodium redistribution, which have significant impacts on the core characteristics such as the multiplication factor and sodium void reactivity worth. The result of reanalysis indicated that the sodium void reactivity worth of the core became higher than that evaluated in the past study, so the redesign of the core was performed to improve the sodium void reactivity worth. To redesign the core, correlations of the sodium void reactivity worth and the dimension of the core and fuel subassemblies was investigated by survey calculations. Based on the results, specifications of the redesigned core were selected. The characteristics of the redesign core were evaluated. To verify the deterministic calculation results, the core characteristics of the redesign core were compared with those by a contentious-energy Monte Carlo simulation with precise geometry modeling, which can provide reference solutions. The both calculations agreed well, and the improvements of core characteristics of the redesign core were verified.

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