超临界水冷堆燃料组件及堆芯方案简化设计研究  

Research on Simplified Assembly and Core Structure Design of SCWR

作　　者：姚磊 夏榜样[1] 卢迪[1] 王连杰[1] 李翔[1] 王诗倩[1] 李庆[1] Yao Lei;Xia Bangyang;Lu Di;Wang Lianjie;Li Xiang;Wang Shiqian;Li Qing(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213

出　　处：《核动力工程》2020年第4期45-49,共5页Nuclear Power Engineering

摘　　要：为解决超临界水冷堆中子慢化不足的问题,采用在燃料组件中设置"水棒"或者加入固体慢化剂的设计方法,同时堆芯冷却剂采用多流程流动方案,导致燃料组件和堆芯结构复杂化,并向堆内引入较多强中子吸收结构材料。因而基于CSR1000研究结果,开展了简化超临界水冷堆燃料组件及堆芯结构设计。研究结果有效简化了超临界水冷堆燃料组件和堆芯结构。To solve the problem of insufficient neutron moderation of the super critical water-cooled reactor(SCWR), the water rod or the adding of the solid moderator is commonly used in assemblies, and a multi-pass flow scheme is adopted, which resulting in the complication of the fuel assembly and the core structure, and the strong neutron absorbing materials are introduced into the reactors. Based on the result of CSR1000 study, the simplification of assembly and core structure was carried out. The results significantly simplified the assembly and core structure of SCWR.

关 键 词：超临界水冷堆 简化 堆芯概念设计 

分 类 号：TL329[核科学技术—核技术及应用]