基于任意三角形网格的中子扩散变分节块法  

Neutron Diffusion Variational Nodal Method Based on Arbitrary Triangular Mesh

作　　者：尚文 庄坤 李婷[1] 汤晓斌[1,2] 于东森 SHANG Wen;ZHUANG Kun;LI Ting;TANG Xiaobin;YU Dongsen(College of Material Science and Technology,Nanjing University of Aeronautics and Astronautics,Nanjing 211106,China;Key Laboratory of Nuclear Technology Application and Radiation Protection in Astronautics(Nanjing University of Aeronautics and Astronautics),Ministry of Industry and Information Technology,Nanjing 211106,China)

机构地区：[1]南京航空航天大学材料科学与技术学院,江苏南京211106 [2]南京航空航天大学,空间核技术应用与辐射防护工业和信息化部重点实验室,江苏南京211106

出　　处：《原子能科学技术》2021年第8期1440-1447,共8页Atomic Energy Science and Technology

基　　金：南京市留学人员科技创新项目(YQR19037);中国博士后基金站前特别资助项目(2019TQ0148);中央高校基本科研业务费项目(NS2019036);空间核技术应用与辐射防护工业和信息化部重点实验室开放基金(NJ2020017-1);江苏省博士后基金(YBA20016)。

摘　　要：传统的基于矩形和六角形几何的堆芯计算程序已不适用于具有复杂几何的新型反应堆堆芯计算,本文开展了基于任意三角形网格的多群中子扩散变分节块方法研究。首先,采用ANSYS软件对计算区域进行三角形网格剖分,并利用坐标变换将任意三角形变换为正三角形;其次,采用Galerkin变分技术建立包含节块中子平衡方程的泛函,将三角形节块内变量利用正三角形内正交基函数进行展开;最后,利用变分原理,获得中子通量密度与节块边界上分中子流的响应关系,并基于传统的源迭代法对其进行求解。基于上述理论模型开发了程序TriVNM,并采用不同几何基准题进行了验证。结果表明,TriVNM计算的堆芯k_(eff)和归一化功率分布与参考解吻合较好,该计算方法适用于复杂几何堆芯扩散计算。The traditional core calculation code based on rectangular and hexagonal geometry cannot be applied to the calculation of new type reactors with complex geometry,the study of multi-group neutron diffusion variational nodal method based on arbitrary triangular meshes was carried out in this paper.Firstly,ANSYS program was used to divide the calculation area into arbitrary triangular meshes,which was then transformed into regular triangles by coordinate transformation method.Secondly,the Galerkin variation technique was employed to establish the functional containing the nodal neutron balance equation and the internal variables of the triangular nodal were expanded using the orthogonal basis functions of the regular triangle.Finally,the variational principle was used to obtain the response relationship between the neutron flux and the surface neutron current,and then the traditional source iteration method was carried out to solve the equations.The code named TriVNM was developed based on the above theoretical model,and verified by diffusion benchmark with different geometries.The results show that the k_(eff) and relative power distribution calculated by TriVNM agree well with the reference results,and this method can be applied to diffusion calculation for reactor core with complex geometry.

关 键 词：变分节块法 中子扩散 任意三角形网格 ANSYS 坐标变换 

分 类 号：TL3[核科学技术—核技术及应用]