Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (9): 90604-090604.doi: 10.11889/j.0253-3219.2018.hjs.41.090604

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles    

Heat transfer performance of inert matrix dispersion pellet based on finite element analysis

LU Zhiwei, ZHANG Yongdong, LI Lei, LIU Tong, XUE Jiaxiang   

  1. Nuclear Fuel Research and Development Center, Department of ATF R & D, Shenzhen 518026, China
  • Received:2017-10-26 Revised:2018-05-16 Online:2018-09-10 Published:2018-09-12
  • Supported by:
    Supported by National Major Special Projects (No.2015ZX06004-001)

Abstract: [Background] Inert matrix dispersion pellet (IMDP), based on the fuel technology of high temperature gas cooled reactor, a type of accident tolerant fuel, takes inert material as matrix, has high thermal conductivity compared to UO2.[Purpose] In this study, effect of temperature, burnup, thermal barrier between tristructural isotropic (TRISO) and matrix on the effective thermal conductivity (ETC) of the IMDP is studied by finite element analysis (FEA) method.[Methods] A FEA model is developed by ABAQUS combined its secondary development function.[Results] The ETC of IMDP decreases as temperature and burnup increases. Under normal operation condition, the centerline temperature of IMDP is 400℃ or more lower than UO2. When the thermal barrier between TRISO and matrix increases from 0 to 4×10-4 m2·℃·W-1, the ETC of IMDP decreases approximately 16% and 19% respectively at beginning of life (BOL) and middle of life (MOL).[Conclusions] IMDP has superior heat transfer performance than UO2. Thermal barrier between TRISO and matrix has more significant impact on BOL IMDP than MOL IMDP. Thermal barrier between 0 to 4×10-4 m2·℃·W-1 has more significant impact on ETC of IMDP than other values.

Key words: Accident tolerant, Inert matrix, Nuclear fuel, Heat transfer

CLC Number: 

  • TL33