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Fourteen Fe–Cr–Al alloys with systematically varied Cr and Al compositions were irradiated at 350 °C to 0.24 dpa by 10.5 MeV self-ions as model alloys for the Fe–Cr–Al (oxide dispersion strengthened: ODS) alloys being developed as accident tolerant fuel (ATF) cladding for light water reactors. Three dose rates (8 ×10−6, 8 ×10−5, and 8 ×10−4 dpa/s) were selected to predict the formation behavior of Cr-rich precipitates (CrRP) under neutron irradiation conditions. The effects of Cr, Al composition, and dose rate on the CrRP formation behavior were evaluated using a three-dimensional atom probe (3DAP) analysis. The the CrRP number density, volume fraction, and Cr concentration increase with increasing Cr composition, decreasing Al composition, and decreasing dose rate. Multiple regression analysis showed that in addition to these primary effects, there was an interaction between them on the CrRP volume fraction: (1) the higher the Al composition, the smaller the increase in the CrRP volume fraction with increasing Cr composition, and (2) the lower the Cr composition, the smaller the increase in the CrRP volume fraction with the decreasing Al composition and dose rate.

権利情報:

• Creative Commons BY-NC-ND Attribution-NonCommercial-NoDerivs 4.0 International
  

キーワード: Accident tolerant fuel cladding, Fe-Cr-Al alloys, Cr-rich precipitate, Ion irradiation, Dose rate, 3D atom probe

刊行年月日: 2024-07-06

出版者: Elsevier BV

掲載誌:

• Journal of Nuclear Materials (ISSN: 00223115) vol. 600 155271

研究助成金:

• 日本学術振興会 22H02013

原稿種別: 著者最終稿 (Accepted manuscript)

MDR DOI: https://doi.org/10.48505/nims.5238

公開URL: https://doi.org/10.1016/j.jnucmat.2024.155271

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更新時刻: 2025-01-06 11:05:02 +0900

MDRでの公開時刻: 2026-07-05 14:28:31 +0900