Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (10): 100604-100604.doi: 10.11889/j.0253-3219.2016.hjs.39.100604

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Accident analyses of uncontrolled rod cluster control assembly bank withdrawal for 10-MWt thorium-based molten salt reactor-solid fuel

JING Jianping1, LIU Yaning2, JIA Bin1, GAO Xinli1, SUN Wei1, ZUO Jiaxu1, ZHANG Chunming1   

  1. 1 Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing 100082, China;
    2 Institute of Process Engineering, Chinese Academy of Sciences, Beijing 100190, China
  • Received:2016-06-02 Revised:2016-08-17 Online:2016-10-10 Published:2016-10-13
  • Supported by:

    Supported by Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA02050500)


Background: Thorium-based molten salt reactor nuclear power system project is one of the "Strategic Priority Program" of Chinese Academy of Sciences, and its strategic goal is to develop the fourth generation moltensalt cooled fission reactor nuclear power system. Based on the system design of 10-MWt molten salt reactor-solid fuel, a safety analysis software is developed for the pebble bed reactor system and verified the correctness and accuracy for the high-temperature gas-cooled reactor of results calculated via this software program. Purpose: This study aims at accident analyses of uncontrolled rod cluster control assembly bank withdrawal for thorium molten salt reactor-solid fuel (TMSR-SF) by using the developed program. Methods: The TMSR-SF reactor core model is built according to the designed parameters. Analyses of the impacts of different shutdown limits and shutdown signals on the withdrawal accident of the TMSR-SF uncontrolled rod cluster control assembly bank is carried out through the safety analysis models such as neutron kinetics model, fluid flow and heat transfer model, control model, etc., in the developed program. Results: In the withdrawal accident of the uncontrolled rod cluster control assembly bank of the TMSR-SF, the maximum temperature of the reactor fuel temperature is no more than 860℃. Conclusions: Computional results show that the higher the limit value of over power shutdown is, the greater the outlet temperature is; the longer the signal delay time is, the later the reactor shutdown happens, and the higher the core power and fuel temperature is. Compared with the limit value of shutdown, the outlet temperature reaches the limit later in time sequence, the maxumum fuel temperature is much lower than the fuel pebble melting temperature limit of 1 600℃ under no circumstances.

Key words: TMSR-SF, Safety analysis, Uncontrolled rod cluster control assembly bank withdrawal, Application development

CLC Number: 

  • TL99