摘要
基于蒙特卡罗粒子输运程序MCNP与自主开发的子通道热工水力学程序SubTH,开发了棒状氢化锆慢化钍基熔盐堆燃料组件稳态核热耦合程序MCNP-SubTH,解决核热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。MCNP-SubTH通过外耦合的方式进行MCNP和SubTH之间的数据交换,将MCNP计算得到的功率场加载到SubTH的求解文件中,然后将SubTH计算得到的密度和温度场更新到MCNP的输入卡中,实现程序迭代计算。分模块验证了MCNP-SubTH的准确性,并用MCNP-SubTH对棒状氢化锆慢化钍基熔盐堆燃料组件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 Monte Carlo particle transport code MCNP and self-developed sub-channel thermal-hydraulic code SubTH,a code system MCNP-SubTH coupling neutronics with thermal-hydraulics was developed,which was suitable for steady state analysis for a thorium molten salt reactor moderated by zirconium hydride rod(ZrH-MSR).It solved the difficulties in the neutronics and thermal-hydraulics coupling code due to different mesh types,and has a general validity.MCNP-SubTH exchanged data between MCNP and SubTH by an external coupling.The power density field obtained from MCNP was provided as a SubTH solution file to give a user-specified source term,and then the density and temperature field from SubTH was updated and as a new MCNP input file by MCNP-SubTH to realize iterative calculation.The accuracy of MCNP-SubTH was verified by each relatively independent module.MCNP-SubTH application in the fuel assembly of ZrH-MSR was studied,and its validity was verified.
作者
朱帆
伍建辉
余呈刚
马玉雯
陈金根
蔡翔舟
ZHU Fan;WU Jianhui;YU Chenggang;MA Yuwen;CHEN Jingen;CAI Xiangzhou(Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China;Innovative Academies in TMSR Energy System,Chinese Academy of Sciences,Shanghai 201800,China;University of Chinese Academy of Sciences,Beijing 100049,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2020年第11期2063-2072,共10页
Atomic Energy Science and Technology
基金
中国科学院战略性先导专项资助项目(XDA02010000)
中国科学院前沿科学重点研究项目资助(QYZDY-SSW-JSC016)。
关键词
MCNP程序
棒状氢化锆慢化钍基熔盐堆
稳态
核热耦合
MCNP code
thorium molten salt reactor moderated by zirconium hydride rod
steady state
coupling of neutronics and thermal-hydraulics
