Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (6): 60602-060602.doi: 10.11889/j.0253-3219.2017.hjs.40.060602

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Feasibility of DRAGON&DONJON code for MSR core burnup calculation

ZHAO Wenbo, XIE Jinsen, XIE Qin, CHEN Zhenping, ZENG Wenjie, LIU Zijing, HE Lihua, YU Tao   

  1. School of Nuclear Science and Technology, University of South China, Hengyang 421001, China
  • Received:2016-11-28 Revised:2016-12-26 Online:2017-06-10 Published:2017-06-06
  • About author:10.11889/j.0253-3219.2017.hjs.40.060602
  • Supported by:
    Supported by National Natural Science Foundation of China (No.11305088), Natural Science Foundation of Hunan Province (No.14JJ2088)

Abstract: Background:Simplify DRAGON&DONJON lattice-core "two step" process reasonably, this method can be applied to any reactor and any working condition. Purpose: This study aims at verifying the feasibility of using DRAGON&DONJON physical analysis for burning TRU and ThU fuel in molten salt reactor (MSR) by combination of reactor Monte Carlo code (RMC) and Monte Carlo neutron particle transport code (MCNP). Methods:Both the molten salt breeder reactor (MSBR) and molten salt advanced reactor transmuter (MOSART) reactor were taken as examples for comparison and analysis. RMC program was employed to verify accuracy of burnup calculated by DRAGON program whilst MCNP program was used to verify both the accuracy of lattice homogenization embedded in DRAGON program and the few group cross-section call and diffusion in whole reactor adopted in DONJON program. Results:The results show that DRAGON program can be used in MSR for burning TRU and ThU fuel. The calculation errors of fast spectrum and thermal spectrum diffusion are less than 0.001 in critical calculation. Conclusion:DRAGON&DONJON is suitable for physical analysis of TRU and ThU fuel burning in MSR.

Key words: MSR, Lattice homogenization, ThU, TRU

CLC Number: 

  • TL99