Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (3): 30601-030601.doi: 10.11889/j.0253-3219.2020.hjs.43.030601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Study on the sustainability of thorium uranium fuel in Molten Salt Reactor under on-line plutonium loading model

Changqing YU1,2,Guifeng ZHU1(),Shaopeng XIA1,Yang ZOU1,Xiaohan YU1()   

  1. 1.Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
    2.University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2019-11-08 Revised:2020-01-04 Online:2020-03-15 Published:2020-03-24
  • Contact: Guifeng ZHU,Xiaohan YU E-mail:zhuguifeng@sinap.ac.cn;yuxiaohan@sinap.ac.cn
  • About author:YU Changqing, male, born in 1994, graduated from Soochow University in 2017, master student, focusing on physical design on MSR
  • Supported by:
    Strategic Priority Research Program of Chinese Academy of Sciences(XDA02010000);Frontier Science Key Program of Chinese Academy of Sciences(QYZDY-SSW-JSC016);Sailing Plan of Shanghai(Y931021031)

Abstract: Background

Thorium-uranium sustainability of molten salt reactor usually relies heavily on online reprocessing technology, which is still immature at the present.

Purpose

The study aims to use reactor-grade plutonium online to achieve233U self-sustaining and burn reactor-grade plutonium based on the FLiBe carrier salt and Th/233U starter reactor.

Methods

Based on Scale6.1, the program of molten salt reactor feeding and reprocessing sequence (MSR-RRS) was developed. The database ENDF /B-VII Library of group 238 was adopted for simulation.Single cell models were used to analyze the performance of233U self-sustaining and plutonium utilization at different molten salt volume fraction (VF) and neutron loss ratio.

Results & Conclusions

It is found that233U self-sustaining could be achieved in a large range from 10%VF to 85%VF, and233U have the best breeding ability at about 43%VF, of which the utilization of plutonium is worst. When the VF becomes smaller or larger, the utilization of plutonium always becomes smaller. It is more beneficial to burn plutonium in the low VF region. When VF is 10%~15%, the burning ratio of plutonium is the highest, corresponding to 75%. In addition, the neutron loss ratio is positively proportional to the burnup of plutonium, and has little influence on the self-sustaining performance of233U.

Key words: Thorium molten salt reactor, Thorium-uranium sustainability, Reactor-grade plutonium, Fuel utilization

CLC Number: 

  • TL99