Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (2): 20605-020605.doi: 10.11889/j.0253-3219.2018.hjs.41.020605

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Uncertainty analysis of reactor pressure vessel fast neutron fluence calculation

ZHANG Bin1, ZHENG Junxiao2, LI Xiaojing3, BAO Boyu1, CHEN Yixue1   

  1. 1. North China Electric Power University, Beijing 102206, China;
    2. China Nuclear Power Technology Research Institute, Shenzhen 518026, China;
    3. China Nuclear Power Engineering Co., Ltd., Beijing 100840, China
  • Received:2017-09-18 Revised:2017-11-06 Online:2018-02-10 Published:2018-02-06
  • Supported by:
    Supported by National Natural Science Foundation of China (No.11505059, No.11575061)

Abstract: [Background] The precise calculation of reactor pressure vessel (RPV) fast neutron fluence can be used to evaluate the materials irradiation damage during the designed lifetime and support analyses for a potential plant life extension. The uncertainties of reactor materials and geometry, nuclear data, neutron source and transport solving process can affect the reliability of fast neutron fluence simulation results. [Purpose] This paper aims to effectively evaluate the calculation results by thorough analysis of the uncertainties described above. [Methods] This paper analyzed the main origin of uncertainties in the RPV fast neutron fluence calculation and focus on the effect of the neutron source processing method, the Legendre expansion of the anisotropic scattering cross section and spatial discretization method of transport equation. [Results and Conclusion] Modeling of fuel assemblies usually produces a deviation about 20%, the effect of fission nuclide and transport correction methods are about 10%. Through analyses we can understand the weak aspects of the calculation methods and improve the accuracy of calculation results.

Key words: Radiation shielding, Fast neutron fluence, Reactor pressure vessel, Discrete ordinates method

CLC Number: 

  • TL328