SVBR-100铅铋冷却反应堆热工水力仿真分析  

Thermal-Hydraulic Simulation Analysis of SVBR-100 Lead Bismuth Cooled Reactor

作　　者：姜旭辉 林萌[1] JIANG Xu-hui;LING Meng(School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai 200240,China)

机构地区：[1]上海交通大学核科学与工程学院,上海200240

出　　处：《计算机仿真》2024年第1期301-305,327,共6页Computer Simulation

摘　　要：为了研究铅铋堆的热工水力特性和控制方案,对热工水力程序RELAP5进行正确地扩展改造后,建立铅铋堆的对象模型,并对模型进行稳态和瞬态情况下的仿真特性分析。仿真结果表明,稳态计算结果与设计值基本一致;瞬态计算结果与物理原理和经验知识一致;瞬态时与水堆对比结果表明铅铋堆引入变化后反应性和核功率参数变化幅度更小,稳定更快,堆芯温度和燃料表面温度稳定时间更短,说明相较于水堆,铅铋堆本身具有的更好的自稳自调特性使其更具发展潜力。In order to study the thermal-hydraulic characteristics and control scheme of the lead-bismuth reactor,after the thermal-hydraulic program RELAP5 is correctly expanded and transformed,the object model of the leadbismuth reactor is established,and the simulation characteristics of the model under steady-state and transient conditions are analyzed.The simulation results show that the steady-state calculation results are consistent with the design values.The transient calculation results are consistent with physical principles and empirical knowledge.Compared with the water reactor in a transient state,the results show that the reactivity and nuclear power parameters of the lead-bismuth reactor change less and stabilize faster,and the stability time of core temperature and fuel surface temperature is shorter,indicating that compared with the water reactor,the lead-bismuth reactor has better self-stability and self-regulation characteristics,which makes it have more development potential.

关 键 词：铅铋堆 热工水力 对象模型 

分 类 号：TP391.9[自动化与计算机技术—计算机应用技术]