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
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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。Abstract: 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.
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Key words:
- SCWR /
- Simplification /
- Core conceptual design
期刊类型引用(2)
1. 张乐福，黄涛，苏豪展，高阳，郭相龙，沈朝，陈凯. 超临界水冷堆候选包壳材料研究进展与思考. 核动力工程. 2025(01): 183-190 . 
本站查看2. 娄磊，王连杰，魏彦琴，黄世恩，蔡云，陈亮，刘晓黎，李司南，唐霄，张策. 六边形套管型燃料堆芯临界物理试验方案设计研究. 核动力工程. 2021(05): 256-260 . 本站查看其他类型引用(0)
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