Development of Radiation Porosity in the Material of Fuel-Element Cladding Produced by Different Technologies for Fast Neutron Reactors and Its Influence on the Fuel Assembly Service Life in the BN-600 Reactor

被引：0
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作者：
A. R. Isinbaev
I. A. Portnykh
A. V. Kozlov
机构：
[1] Institute of Reactor Materials,
[2] Ural Federal University,undefined
来源：
Physics of Metals and Metallography | 2022年 / 123卷
关键词：
austenitic steel; neutron irradiation; swelling; point defects; vacancy migration; critical void diameter; BN-600 reactor; fuel cladding; swelling prediction;
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页码：528 / 534
页数：6
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