超临界水冷堆CSR150概念设计  

Conceptual Design of Supercritical Water-cooled Reactor CSR150

作　　者：甯忠豪 王连杰[1] 卢迪[1] 夏榜样[1] 黄彦平[2] 陈兴 Ning Zhonghao;Wang Lianjie;Lu Di;Xia Bangyang;Huang Yanping;Chen Xing(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;CNNC Key Laboratory Thermal-Hydraulics Technology,Nuclear Power Institute of China,Chengdu,610213,China;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 [2]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,成都610213 [3]中国核动力研究设计院,成都610213

出　　处：《核动力工程》2023年第S01期9-13,共5页Nuclear Power Engineering

基　　金：国家自然科学基金(12075228);国家重点研发计划国际科技合作专项(2018YFE0116100)。

摘　　要：超临界水冷堆(SCWR)是第IV代核能系统候选堆芯之一。在中国核动力研究设计院提出的中国超临界水冷堆(CSR1000)概念设计方案的基础上,提出了超临界技术示范堆(CSR150)概念设计方案。本文开展了CSR150堆芯设计研究,堆芯采用45盒燃料组件设计,通过燃料富集度分区及双流程冷却剂流动方案设计,提升冷却剂出口温度并降低燃料包壳温度。研究分析表明,本文方案中功率分布、燃料包壳温度等关键参数满足CSR150设计目标和设计准则要求。Supercritical water-cooled reactor(SCWR) is regarded as one of the GEN IV nuclear reactors.Based on the conceptual design of CSR1000 proposed by NPIC,the conceptual design of supercritical water-cooled demonostration reactor CSR150 is proposed.The core design of CSR150 is studied in this paper.The core consists of 45 fuel assembles,and the fuel enrichment zoning and two-pass coolant flow scheme are adopted to increase the coolant outlet temperature and reduce the fuel cladding temperature.The study shows that the key parameters such as power distribution and fuel clad temperature meet the design objectives and criteria of CSR150.

关 键 词：超临界水冷堆(SCWR) 中国超临界水冷堆(CSR1000) 超临界技术示范堆(CSR150) 

分 类 号：TL333[核科学技术—核技术及应用]