Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (9): 90601-090601.doi: 10.11889/j.0253-3219.2018.hjs.41.090601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Multi-temperature cross section generation method in unresolved resonance energy region based on Neville interpolation

CHEN Rui1,2, ZHOU Shumin1,2   

  1. 1 Jiangxi Engineering Research Center of Process and Equipment for New Energy, East China University of Technology, Nanchang 330013, China;
    2 School of Mechanical and Electronic Engineering, East China University of Technology, Nanchang 330013, China
  • Received:2018-04-25 Revised:2018-06-04 Online:2018-09-10 Published:2018-09-12
  • Supported by:
    Supported by National Natural Science Foundation of China (No.11565002), Jiangxi Provincial Education Department Project (No.GJJ150558) and Open Project Program of Jiangxi Engineering Research Center of Process and Equipment for New Energy (No.JXNE2017-04)

Abstract: [Background] For a nuclear energy system with fast neutron spectrum, the cross section in unresolved resonance energy region is affected by the temperature effect and changes, hence, it is not possible to accurately obtain the section of each energy corresponding to the resonance peak in the energy region. When calculating the cross sections under various temperatures, the calculation method different from the resolved resonance energy region must be taken.[Purpose] This study aims to propose a novel multi-temperature cross section generation method to improve efficiency with given accuracy.[Methods] Based on the investigation of the status of the worldwide on-the-fly nuclear cross section generation methods for the unresolved resonance energy region in Monte Carlo neutron transport, the Neville interpolation is used for better efficiency according to the cross section features of probability table at different temperatures. This multi-temperature cross section generation method was verified on two publicly available reactor core models.[Results] Performance test results on international fast reactor core models, i.e., Bigten1 and Bigten2, show that the deviation of the method and the reference value is less than 10 pcm, which proves the accuracy and effectiveness of the method.[Conclusion] The accuracy and effectiveness of this proposed method showed its applicability for reactor multi-physical coupling simulation.

Key words: Neutron cross section, Monte Carlo, Unresolved resonance energy region, Neville interpolation

CLC Number: 

  • TL329+.2