基于中子随机输运理论的物理-热工耦合研究  

Research on Coupling of Neutronics and Thermal-Hydraulics Based on Stochastic Method of Neutron Transport

作　　者：李林森[1,2] 王侃[2] 袁昊民[2] 臧金光[2,3] 

机构地区：[1]国核(北京)科学技术研究院,北京100029 [2]清华大学工程物理系,北京100084 [3]中国核动力研究设计院,四川成都610041

出　　处：《原子能科学技术》2013年第B06期291-294,共4页Atomic Energy Science and Technology

基　　金：国家重点基础研究发展计划资助项目(2007CB209807)

摘　　要：基于随机输运理论的中子动力学与热工水力的耦合可实现对不同程序的控制和数据传递。本工作研究基于单根燃料棒和3×3燃料棒束的MCNP5程序与CFD程序CFX的耦合。使用该耦合程序对先进球床高温反应堆(PB-AHTR)的堆芯进行计算,并与MCNP5与RELAP5-3D耦合程序的计算结果进行比较。由计算结果可见:在不同初始状态下,有效增殖因数经若干耦合计算后均趋于稳定,但伴随一定波动。结果表明,中子动力学与CFD的瞬态耦合是可行的,但其计算精确度和实用性需进一步验证研究。The coupling of neutronics and thermal-hydraulics based on stochastic method of neutron transport is able to control the different codes and transfer data.The coupling methods of MCNP5 and CFX based on a single fuel rod channel model and a 3×3 rod bundle model were studied.Based on the research above,the coupling of MCNP5 and CFX applied to a Pebble Bed-Advanced High Temperature Reactor（PB-AHTR） was studied and validated by comparing to the results of the coupling of MCNP5 and RELAP5-3D.The results of the coupled calculations indicate that the effective multiplication factor will stay stable after several coupled iterations with some fluctuation.The research results demonstrate that the feasibility of the coupled code is approved,but the accuracy of the coupled calculation needs to be improved in the future research.

关 键 词：物理-热工 耦合 PB-AHTR CFX MCNP RELAP5-3D 

分 类 号：TL329[核科学技术—核技术及应用]