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

引用

页码：122 / 128