Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (5): 50605-050605.doi: 10.11889/j.0253-3219.2016.hjs.39.050605


Preliminary analysis of Th-U conversion performance in a ZrH-moderated molten salt reactor

WU Pan1,2, CAI Xiangzhou2, YU Chenggang2, CHEN Jingen2, XU Gang1   

  1. 1. Shanghai University, Shanghai 200444, China;
    2. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China
  • Received:2016-01-12 Revised:2016-03-22 Online:2016-05-10 Published:2016-05-12
  • Supported by:

    Supported by Science and Technology Project of Chinese Academy of Sciences(No.XDA02010100)


Background: The neutron spectrum plays an important role in thorium-based fuel utilization efficiency and temperature feedback coefficient concerning reactor operation safety, so it is very important to study the new moderator material used in molten salt reactor(MSR). Purpose: This study aims to analyze the thorium-uranium conversion performance of a ZrH-moderated molten salt reactor and analyze the feasibility of ZrH as moderator in molten salt reactor. Methods: SCALE program is used to calculate neutron spectrum, thorium uranium conversion ratio, 233U concentration, total temperature feedback coefficient and burnup calculation with different lattice parameters. Results: The thorium uranium conversion ratio and total temperature feedback coefficient can be improved significantly by reducing lattice size or increasing salt volume ratio; the initial 233U concentration for start reactor can be easily controlled under 2.5×10-2 when the volume share of added ZrH is 0.1. Conclusion: Compared to the graphite-moderated MSR, ZrH-moderated MSR reduces initial 233U inventory and transuraniums(TRUs) production, and makes its core more compact.

Key words: ZrH moderator, MSR, Thorium uranium conversion performance, 233U inventory

CLC Number: 

  • TL329