Synchronized forward-adjoint neutron transport using method of characteristics

作     者：Shokueifar, V. Zangian, M. Minuchehr, A. Zolfaghari, A. 

作者机构：Shahid Beheshti Univ Dept Nucl Engn POB *** Tehran Iran 

出 版 物：《PROGRESS IN NUCLEAR ENERGY》 (核能进展)

年 卷 期：2016年第92卷第0期

页      面：211-219页

核心收录：

学科分类：08[工学] 0827[工学-核科学与技术] 

主　　题：Multigroup neutron transport code Method of characteristics Forward-adjoint flux 2D geometry Lattice-universe base geometry model 

摘      要：The method of characteristics has been widely used for neutron transport calculations in lattice physics computations. This method recently has attracted a lot of attention for whole core calculation because of its flexibility in geometry definition and to highly impose parallelization. One area of whole core calculation is perturbation calculation that needs forward-adjoint flux. The objective of the work presented in this paper is to develop a synchronized forward-adjoint neutron transport solver embedding in FAMOC code. FAMOC is a new neutron transport code based on method of characteristics that is currently under development at Shahid Beheshti University (SBU). It is capable of simulating 2D models based on combinatorial geometry with first or second-order surfaces, and a multilevel lattice-universe base geometry model to rectangularly simulate. In this code, the same tracking data is used to compute forward and adjoint average flux. The forward and adjoint effective multiplication factor, and flux obtained by FAMOC code for 2D benchmark of C5G7 were found to be in good agreement with references. (C) 2016 Elsevier Ltd. All rights reserved.