Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (4): 40008-040008.doi: 10.11889/j.0253-3219.2020.hjs.43.040008

• SPECIAL SECTION ON THE 11TH NATIONAL CONFERENCE ON NEW AND RESEARCH REACTORS (PART I) • Previous Articles     Next Articles

Application of PROTEUS-MOC for the steady state simulations of TREAT

Guangchun ZHANG1,2,Jie LIU1,2(),Won Sik YANG3   

  1. 1.Science and Technology on Parallel and Distributed Processing Laboratory, National University of Defense Technology, Changsha 410073, China
    2.Laboratory of Software Engineering for Complex Systems, National University of Defense Technology, Changsha 410073, China
    3.University of Michigan, Ann Arbor, Michigan 48105, United States
  • Received:2020-02-24 Revised:2020-03-30 Online:2020-04-15 Published:2020-04-20
  • Contact: Jie LIU E-mail:liujie@nudt.edu.cn
  • About author:ZHANG Guangchun, male, born in 1986, graduated from Xi’an Jiaotong University with a doctoral degree in 2015, focusing on transport solution methods and parallel computing algorithm
  • Supported by:
    National Key Research and Development Program of China(2018YFB0204301)

Abstract: Background

The transient reactor test facility (TREAT) is a test reactor designed to evaluate the performance of nuclear fuels and other structural materials. TREAT is characterized by its complex structure, the use of air as coolant and graphite as moderator, and strong neutron leakage and heterogeneities in both the radial and axial directions. These characteristics challenge most deterministic neutronics simulation codes. The PROTEUS-MOC code, developed at the Argonne National Laboratory in collaboration with the University of Michigan, adopts the 2D method of characteristics (MOC) and the 1D discontinuous Galerkin finite element method (FEM) to treat the radial and axial distributions of angular flux, respectively.

Purpose

This study aims to evaluate the accuracy and efficiency of PROTEUS-MOC code in steady-state neutronics calculation of TREAT.

Methods

The 3D TREAT model was radially discretized into unstructured mesh grids and axially discretized into a stack of planes. The macroscopic cross sections were obtained using the Serpent Monte-Carlo code.

Results

PROTEUS-MOC demonstrates satisfactory precisions of eigenvalues by accurately capturing the strong neutron leakage of TREAT. Compared with the eigenvalues obtained by Monte Carlo code Serpent, the relative difference of the eigenvalues obtained by PROTEUS-MOC is merely 0.12%. Additionally, the results showed that the acceleration method TLPCMFD (two-level pCMFD) adopted in PROTEUS-MOC is very effective, speeding up the simulation by a factor of 26.

Conclusions

This work demonstrates that PROTEUS-MOC is capable of producing faithful and accurate results for neutronics calculations of reactor problems with strong neutron leakage and heterogeneities.

Key words: Transient reactor test facility, Neutronic simulations, Method of characteristics, Discontinuous finite element method

CLC Number: 

  • TL323