摘要
基于中子物理计算程序包SRAC与计算流体力学软件CFX,开发了稳态情况下固态燃料熔盐堆的核热耦合程序SCBAT,解决了一般稳态3D物理-3D热工耦合程序因网格类型不同难以耦合的问题,程序具有普适性。SCBAT通过SRAC和CFX之间的数据交换实现稳态核热耦合,可将SRAC计算的功率场加载到CFX的求解文件中,将CFX计算的温度场加载到SRAC的输入卡中,此外具备带控制棒临界搜索的燃耗计算功能。分模块验证了SCBAT的有效性,并用SCBAT对10 MW固态燃料熔盐堆进行了稳态核热耦合计算,验证了核热耦合方法的有效性。
Based on the neutronics calculation code package SRAC and the computational fluid dynamics code CFX, a code system SCBAT coupling neutronics with thermal-hydraulics for solid fuel molten salt reactor at steady state was developed. SCBAT transfers data between SRAC and CFX to realize the neutronics and thermal-hydraulics coupled calculation. Power density field result from SRAC can be passed to CFX-Solver to give a user-specified source term and temperature field result from CFX can be passed to SRAC input file by SCBAT. Meanwhile, SCBAT can realize the burn up calculation with critical search using the control rods. SCBAT validity was verified by module. SCBAT application in 10MW solid fuel molten salt reactor was studied.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2017年第2期1-5,共5页
Nuclear Power Engineering
基金
中国科学院战略性先导科技专项资助项目(XDA02010200)
关键词
固态燃料熔盐堆
核热耦合
临界搜索
燃耗
Solid fuel molten salt reactor, Coupling of neutronics and thermal-hydraulics,Critical search, Burn up
