Analysis of fracture conditions of Cr-coated Zr alloy claddings under LOCA conditions calculated using FEMAXI fuel performance code

Annals of Nuclear Energy 2026

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Authors: Vu-Nhut Luu, Yoshinori Taniguchi, Yutaka Udagawa, Yudai Tasaki, Jinya Katsuyama

DOI: 10.1016/j.anucene.2026.112114

Cited by: 2

References: 36

Fields of Study & Subjects

Nuclear Materials and Properties Nuclear reactor physics and engineering Nuclear Engineering Thermal-Hydraulics

References 36