Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (2): 20604-020604.doi: 10.11889/j.0253-3219.2017.hjs.40.020604


Effect of different description of neutron source models on neutronics calculation of CFETR

LIU Qi1, XU Kun1, LEI Mingzhun2, SONG Yuntao1,2   

  1. 1. University of Science and Technology of China, Hefei 230031, China;
    2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China
  • Received:2016-10-24 Revised:2016-11-30 Online:2017-02-10 Published:2017-01-24
  • Supported by:

    Supported by National Magnetic Confinement Fusion Energy Development Research Project (No.2013GB113002)


Background: In Tokamak experiment device, the 14-MeV high-energy neutrons which D-T fusion reaction releases may cause a series of problems such as material activation, high thermal loading and so on when they contact surrounding parts, so the relative neutronics calculation in the process of blanket design and optimization is particularly important. Purpose: This study aims to analyze the effect of point source, uniform source, neutron source based on L-mode, H-mode, A-mode respectively on different neutronics calculation. Methods: Using MCNP (Monte Carlo N Particle Transport Code) program based on the Monte Carlo method the neutron transport process is simulated and the effect of different neutron source models is calculated. Results: Different descriptions of neutron source models have less influence on tritium breeding ratio, but obvious effects on neutron wall loading and power density distribution. Conclusion: Therefore, proper neutron source model should be applied to calculate different neutronics.

Key words: Monte Carlo, Neutron source, Tritium breeding ratio, Neutron wall loading, Power density

CLC Number: 

  • TL61+3