Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (6): 60003-060003.doi: 10.11889/j.0253-3219.2020.hjs.43.060003

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

Modeling and analysis of depletion experiment benchmark based on assembly calculation

Tianxiong WANG1,Tengfei ZHANG1(),Haicheng WU2,Xiaojing LIU1,Jinbiao XIONG1,Xiang CHAI1   

  1. 1.School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
    2.Key Laboratory of Nuclear Data, China institute of atomic energy, Beijing 102413, China
  • Received:2020-02-06 Revised:2020-04-09 Online:2020-06-15 Published:2020-06-12
  • Contact: Tengfei ZHANG E-mail:zhangtengfei@sjtu.edu.cn
  • About author:WANG Tianxiong, male, born in 1995, graduated from North China Electric Power University in 2018, master student, focusing on nuclear reactor physics
  • Supported by:
    National Natural Science Foundation Youth Project of China(11805122);National Natural Science Foundation Excellent Youth Project of China(11922505);"New Young Teachers Startup Plan" of Shanghai Jiaotong University

Abstract: Background

Assembly calculation plays an important role in reactor core design. The depletion calculation accuracy of the assembly calculation is of great significance to the power distribution, refueling life and reactivity control design of nuclear reactor core.

Purpose

This study aims to evaluate the accuracy of the multi-group constant library in the neutron depletion calculation and establish a set of depletion experimental calculation model.

Methods

The depletion historical parameters and the final nuclide composition information were provided by the SFCOMPO-2.0 database. The information of the Takahama-3 reactor, H.B. Robinson-2 reactor and Beznau-1 reactor samples were modeled using the DRAGON code. Some simplified methods were applied to some unavailable data information. The numerical results were compared and analyzed with the benchmark results in the SFCOMPO-2.0 database. [Result &

Conclusions

The results show that most of the nuclide productions are in good agreement with the reference value, and the errors are within 10%. Nuclides with large differences between numerical results and benchmark results are discussed simultaneously, and computational results of three reactor samples were compared and analyzed.

Key words: Assembly calculation, SFCOMPO-2.0, Modeling and analysis of depletion experiment benchmark

CLC Number: 

  • TL99