日本原子力学会和文論文誌
Online ISSN : 2186-2931
Print ISSN : 1347-2879
ISSN-L : 1347-2879
論文
ADS用窒化物燃料ふるまい解析コードの整備
柴田 裕樹齋藤 裕明林 博和高野 公秀
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2024 年 23 巻 3 号 p. 74-80

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Partitioning and transmutation techniques for minor actinides have been developed to reduce the radiotoxicity and volume in high-level radioactive wastes. Minor actinide nitride fuel has been chosen as a candidate for the transmutation of long-lived nuclides using an accelerator-driven system. Understanding the irradiation behavior of nitride fuel is important for its design and development; however, experimental data on irradiation tests of actinide nitrides and their solid solutions are scarce. Recently, in JAEA, a nitride fuel performance analysis module based on the light water reactor fuel performance code FEMAXI-7 has been developed to simulate the irradiation behavior of the nitride fuel. In this study, performance analysis was carried out focusing on the pellet-cladding mechanical interaction (PCMI), which was pointed out as the most effective factor in fuel safety during irradiation. Simulation results show that PCMI does not cause the creep rupture of the cladding.

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