超临界水堆CSR1000堆芯设计优化  

Optimization Design for Supercritical Water Reactor CSR1000 Core

作　　者：王连杰[1] 卢迪[1] 陈炳德[1] 姚栋[1] 赵文博[1] 

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610041

出　　处：《核动力工程》2016年第5期161-166,共6页Nuclear Power Engineering

摘　　要：利用开发的超临界水堆(SCWR)堆芯稳态性能分析程序SNTA,研究分析中国百万千瓦级SCWR(CSR1000)优化堆芯燃耗性能、反应性控制能力、功率分布、最大燃料包壳温度和最大线功率密度等稳态性能,并给出与组件功率相匹配的第II流程冷却剂流量分配方案。研究表明,采用本文所述燃料组件及堆芯设计优化方法,可以有效延长堆芯燃耗寿期。An optimization conceptual design of CSR1000 core is proposed. Steady state performance of the proposed core is then studied with the SCWR core steady state analysis code system SNTA. These key parameters such as burnup performance, reactivity control capability, power distribution, maximum fuel cladding temperature and maximum linear power density are analyzed. The relative coolant flow rate of the second flow path which is suited with assembly power is also presented. The study shows that the life of CSR1000 core could be extended effectively with the optimization design for CSR1000 fuel assembly and core.

关 键 词：超临界水堆 堆芯设计优化 稳态性能 堆芯寿期 

分 类 号：TL3[核科学技术—核技术及应用]