Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (6): 60008-060008.doi: 10.11889/j.0253-3219.2020.hjs.43.060008

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

Study on hexagonal integral variational nodal method and acceleration method

Han YIN1,Bin ZHANG2,Xiaojing LIU1,Tengfei ZHANG1()   

  1. 1.School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
    2.Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
  • Received:2020-02-25 Revised:2020-04-24 Online:2020-06-15 Published:2020-06-12
  • Contact: Tengfei ZHANG E-mail:zhangtengfei@sjtu.edu.cn
  • About author:YIN Han, male, born in 1995, graduated from Lanzhou University in 2018, master student, focusing on study of reactor physical numerical calculation method
  • Supported by:
    Youth Program of National Natural Science Foundation of China(11805122);Excellent Youth Program of National Natural Science Foundation of China(11922505)

Abstract: Background

Accurate and efficient neutron calculation method is a prerequisite for fast reactor conceptual design and scheme optimization.

Purpose

The study aims to propose an integral form of variational nodal method to solve the three-dimensional multi-group neutron transport equation with hexagonal geometry.

Methods

The integral method was used to deal with the angular flux within hexagonal nodes while angular flux distributions on nodal interfaces are approximated by even-parity spherical harmonics. Besides, the quasi-reflected interface condition (QRIC) method was employed to reduce the number of interfacial angular terms to save computational costs. Finally, the TAKEDA-4 benchmark was taken for evaluation.

Results

The calculation results of TAKEDA-4 benchmark show that, compared with low angular order approximations, the integral method exhibits superior accuracy than the standard variational node method based on spherical harmonic discretization, and reduces the errors by 2~5 times in eigenvalue. In addition, the joint performance of the integral method and the QRIC method yields a remarkable computational time gain of 33.0 with the P7 angular approximation.

Conclusions

The integral variational node method presented in this paper realizes accurate and efficient simulation of fast reactor in hexagonal geometry.

Key words: Variational nodal method, Hexagonal geometry, Integral method, Quasi-reflected interface condition

CLC Number: 

  • TL99