压水堆各向异性散射的输运修正方法研究  

Transport Correction Method of PWR Anisotropic Scattering

作　　者：田超[1,2] 郑友琦[1] 李云召[1] 于颖锐[2] 刘琨[2] 陈定勇[2] 谢运利 

机构地区：[1]西安交通大学核科学与技术学院,陕西西安710049 [2]中国核动力研究设计院核反应堆系统设计技术重点实验室,四川成都610213

出　　处：《原子能科学技术》2017年第9期1599-1605,共7页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(11605128;11522544)

摘　　要：压水堆燃料组件中子输运计算为堆芯扩散计算提供均匀化群常数,所以如何在考虑中子各向异性散射的情况下得到堆芯扩散计算所需的少群均匀化参数是值得研究的。本文推导了中子输运修正计算方法的理论模型,介绍了Inflow输运修正计算方法的数值求解过程,在Bamboo-Lattice程序中进行了程序实现,并采用基准题算例对各种输运修正计算方法进行了对比分析。结果表明:各种输运修正计算方法中,Inflow输运修正方法在保证计算效率的前提下能得到更高的计算精度。Neutron transport calculation of PWR fuel assembly provides homogenization group constants,hence,it is deserved to research how to obtain few group homogenization parameters required by core diffusion calculation under the condition of considering neutron anisotropic scattering.Theory model of the transport correction calculation methods was derived and numerical solving process of Inflow transport correction calculation method was introduced.The corresponding code was developed in Bamboo-Lattice to verify all of the transport correction calculation methods with benchmarks.The results indicate that Inflow transport correction calculation method shows higher calculation accuracy under the premise of insuring efficiency.

关 键 词：输运计算 输运修正 列输运修正 

分 类 号：TL323[核科学技术—核技术及应用]