Synchronized forward-adjoint neutron transport using method of characteristics

Abstract 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.

[1]  Benoit Forget,et al.  The OpenMOC method of characteristics neutral particle transport code , 2014 .

[2]  Liangzhi Cao,et al.  Auto MOC—A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD , 2008 .

[3]  Mathieu Hursin,et al.  AGENT Code: Open-Architecture Analysis and Configuration of Research Reactors - Neutron Transport Modeling with Numerical Examples , 2004 .

[4]  Igor Zmijarevic,et al.  APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations , 1988 .

[5]  A. Zolfaghari,et al.  Development and validation of a new multigroup Monte Carlo Criticality Calculations (MC3) code , 2015 .

[6]  S. Kosaka,et al.  Transport Theory Calculation for a Heterogeneous Multi-Assembly Problem by Characteristics Method with Direct Neutron Path Linking Technique , 2000 .

[7]  Dan G. Cacuci,et al.  Handbook of Nuclear Engineering , 2010 .

[8]  James Bryce Taylor The development of a three-dimensional nuclear reactor kinetics methodology based on the method of characteristics , 2007 .

[9]  Han Gyu Joo,et al.  Cell Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculations , 2002 .

[10]  Jasmina L. Vujic,et al.  ANEMONA — a neutron transport code for general geometry reactor assemblies based on the method of characteristics and R-function solid modeler , 2001 .

[11]  Ser Gi Hong,et al.  CRX: A code for rectangular and hexagonal lattices based on the method of characteristics , 1998 .