| LOCA工况下锆合金包壳的行为概述 |
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| 引用本文： | 王荣山,耿建桥,翁立奎,张晏玮,王锦红.LOCA工况下锆合金包壳的行为概述[J].材料导报,2011(Z2):501-503. |
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| 作者姓名： | 王荣山 耿建桥 翁立奎 张晏玮 王锦红 |
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| 作者单位： | 苏州热工研究院 |
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| 基金项目： | 国家863计划项目(2008AA031701) |
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| 摘 要： | LOCA作为反应堆运行过程中比较严重的事故,是反应堆基准设计事故;而作为确保裂变产物不泄露的第一道屏障,锆合金优异的性能对于保障LOCA工况下的核安全具有重要意义。阐述了LOCA工况下锆合金的高温氧化行为、抗热冲击性能和力学性能及显微组织等方面的内容,为反应堆用锆合金的研发提供了技术支持。
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| 关 键 词： | LOCA 锆合金 ECR |
Zirconium Alloy Cladding Behaviors under LOCA Condition |
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| WANG Rongshan,GENG Jianqiao,WENG Likui,ZHANG Yanwei,WANG Jinhong.Zirconium Alloy Cladding Behaviors under LOCA Condition[J].Materials Review,2011(Z2):501-503. |
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| Authors: | WANG Rongshan GENG Jianqiao WENG Likui ZHANG Yanwei WANG Jinhong |
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| Affiliation: | (Suzhou Nuclear Power Institute,Suzhou 215004) |
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| Abstract: | As the fatal accident in nuclear power plant,LOCA(loss of coolant accident) is one of most important design-basis accident in light-water reactor.In the condition,zirconium alloy acts as the first shield to prevent the fission product to release from cladding.Zirconium alloy’s behaviors under LOCA condition,high temperature oxidation,thermal shock resistance,mechanical property and microstructure are introduced,and some support for the new zirconium developing program are provided. |
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| Keywords: | LOCA zirconium alloy ECR |
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