摘要
启动系统和启动特性分析是超临界水堆(SCWR)设计的重要组成部分,为了实现全系统启动分析,以SCWR瞬态分析程序SCTRAN为基础,提出了新的宽参数范围的壁面换热模型,在此基础上设计了启动过程的控制系统,包括冷却剂流量、堆芯入口温度、系统压力、堆芯功率、汽鼓水位控制。根据启动各阶段的不同控制目标建立不同的控制方案,并以中国百万千瓦SCWR(CSR1000)为研究对象,建立了包括再循环回路和直流冷却回路的分析模型,提出了采用控制系统的SCWR的4个启动过程。计算结果表明,再循环回路和直流冷却回路在各个启动过程中,各热工参数变化符合预期,最高包壳表面温度不超过限值温度650℃,验证了启动方案的可行性和启动过程的安全性。
The analysis of the startup system and startup characteristics are one important part of SCWRs design.In order to realize the analysis of the whole startup system,this paper proposes the new wall heat transfer model,based on the supercritical transient analysis code named SCTRAN.Then,the paper presents a control strategy for the startup process,including the control of coolant flow rate,core inlet temperature,system pressure,core thermal power,and steam drum water level.Different control schemes are set up according to different control objectives of the startup phases.Based on the CSR1000,an analytical model including the circulation loop and the once-through direct cycle loop is established,and four startup processes with control systems are put forward.The calculation results show that the thermal parameters of the circulation loop and the once-through direct cycle loop meet the expectation,and the maximum cladding surface temperature does not exceed the limit temperature 650℃.The feasibility of the startup scheme and the security of the startup process are verified.
作者
袁园
王丽
罗涵禹
单建强
张小英
王冬青
Yuan Yuan;Wang Li;Luo Hanyu;Shan Jianqiang;Zhang Xiaoying;Wang Dongqing(Sino-French Institute of Nuclear Engineering and Technology,Sun Yat-sen University,Zhuhai,Guangdong,519080,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;School of Nuclear Science and Technology,Xi' an Jiaotong University,Xi' an,710049,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第3期115-120,共6页
Nuclear Power Engineering