Experimental Study of Cr-coated Zirconium Alloy Cladding under Simulated LOCA Conditions

被引：0
|
作者：
Wang, Zhanwei [1 ]
Yan, Jun [1 ]
Peng, Zhenxun [1 ]
Ren, Qisen [1 ]
Liao, Yehong [1 ]
Li, Sigong [1 ]
Zhao, Yahuan [1 ]
机构：
[1] Department of Nuclear Fuel & Material, China Nuclear Power Technology Research Institute Co., Ltd., Guangdong, Shenzhen,518026, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷 / 02期
关键词：
Engineering Village;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Cr-coated zirconium alloy cladding - Ductile to brittle transitions - Fukushima nuclear accidents - High temperature steam oxidation - Highest temperature - Loss of coolant accident - Loss of coolant accident conditions - Loss-of-coolant-accident - Quenching - Steam oxidation
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页码：122 / 128
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