VVER公司
包层(金属加工)
燃尽
材料科学
退火(玻璃)
棒
合金
辐照
横截面
核燃料
锆合金
复合材料
辐射损伤
冶金
核工程
结构工程
核物理学
工程类
物理
替代医学
病理
医学
作者
G. P. Kobylyansky,А. О. Mazaev,Е. А. Zvir,S. G. Eremin,Е. V. Chertopyatov,А. В. Обухов
标识
DOI:10.1134/s2075113322030170
摘要
This article presents the experimental results of mechanical properties of fuel rod claddings from E110 zirconium alloy in the longitudinal direction that operated in fuel assemblies of VVER-1000 nuclear reactors to the fuel burnup of ~20 and ~70 MW d/kg U before and after post-radiation annealing at 380°C for 468 days. The changes in strength and plastic properties of the cladding in longitudinal direction were analyzed in comparison with its properties before and after irradiation and with their changes in the transverse direction. The changes in mechanical properties of the cladding are explained as a function of radiation damage of its structure.
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