Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions
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- 作者：Dong Jun Park ; pdj@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author ; Hyun Gil Kim ; Yang Il Jung ; Jung Hwan Park ; Jae Ho Yang ; Yang Hyun Koo
- 关键词：Light water nuclear reactor ; Fuel cladding ; Cold spraying ; Loss-of-coolant accident ; Mechanical properties
- 刊名：Journal of Nuclear Materials
- 出版年：2016
- 出版时间：15 December 2016
- 年：2016
- 卷：482
- 期：Complete
- 页码：75-82
- 全文大小：3692 K
文摘
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Cr and FeCrAl were coated onto Zr fuel cladding for light water nuclear reactors.
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Mo layer between FeCrAl and Zr prevented inter-diffusion at high temperatures.
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Coated claddings were tested under loss-of-cooling accident conditions.
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Coating improved high-temperature oxidation resistance and mechanical properties.