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作 者:孙志军 王帅[1] 张永领[1] 曹俊杰 刘金龙 SUN Zhi-jun;WANG Shuai;ZHANG Yong-ling;CAO Jun-jie;LIU Jin-long(Nuclear Power Institute of China,Chengdu Sichuan 610213,China;Sichuan Engineering Laboratory for Nuclear Facilities Decommissioning and Radwaste Management,Chengdu Sichuan 610213,China)
机构地区:[1]中国核动力研究设计院,四川成都610213 [2]四川省核设施退役与废物治理工程实验室,四川成都610213
出 处:《装备制造技术》2020年第2期37-41,73,共6页Equipment Manufacturing Technology
摘 要:针对核设施去污设计了超临界二氧化碳去污试验系统,根据去污工艺开展了耐酸碱和耐高压去污容器结构设计,建立了去污容器三维模型和有限元模型。通过有限元分析获得了去污容器应力分布,找到了受力最大位置。通过容器壁厚和内腔过渡圆角半径对容器应力的影响关系分析,为确定结构参数提供了依据。水压试验和去污试验结果表明,该去污容器结构强度和系统匹配性均满足要求。A supercritical carbon dioxide decontamination test system is designed for decontamination of nuclear facilities.According to the decontamination process,a vessel with acid and alkali resistance and high pressure resistance is designed.Meanwhile the 3 D model and the finite element analysis model of the decontamination vessel are established.Through the mechanical analysis,the stress distribution of the decontamination vessel is obtained,and the influence of wall thickness and fillet radius on the stress of the vessel is obtained.The analysis results provide a basis for the determination of structural parameters.The results of water pressure test and decontamination test show that the structural strength and system matching of the decontamination vessel meet the decontamination requirements.
分 类 号:TH122[机械工程—机械设计及理论] TL944[核科学技术—辐射防护及环境保护]
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