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作 者:汪俊 申腾 WANG Jun;SHEN Teng(China Nuclear Power Engineering Co.,Ltd.Reactor Engineering Department,Beijing 100840,China)
机构地区:[1]中国核电工程有限公司反应堆工艺研究所,北京100840
出 处:《核科学与工程》2022年第5期1206-1211,共6页Nuclear Science and Engineering
摘 要:目前国内外压水堆核电厂所使用的核燃料组件逐步向长周期高燃耗转变。高燃耗组件燃料棒锆合金包壳内的氢化物应力再取向现象显著,导致包壳强度和韧性降低,在厂外运输中更易受到外部作用而破裂,失去对燃料芯块的包容限制功能。本文通过对氢化物应力再取向机理的分析,确定乏燃料包壳能够保持强度和韧性的条件,并结合具体型号的乏燃料组件运输容器设计,提出并实践了一种通过容器内温度场分析判断高燃耗乏燃料组件厂外运输条件下保持安全性的方法。At present,the nuclear fuel assemblies used in PWR at home and abroad are gradually changing to long-term high burnup.The hydride stress re-orientation phenomenon in the zircaloy cladding of high burnup assembly is significant,resulting in the reduction of cladding strength and ductility,more vulnerable to external impact and fracture in off-site transportation,and losing the containment and restriction function of fuel pellets.Based on the analysis of the mechanism of hydrides stress re-orientation,this paper determines the conditions under which the spent fuel cladding can maintain the strength and ductility.Combined with the design of specific types of spent fuel assembly transportation container,it proposes and practices a method to judge the safety of high burnup spent fuel assembly under off-site transportation conditions through the analysis of the temperature field in the container.
分 类 号:TL413[核科学技术—核技术及应用]
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