Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (10): 100601-100601.doi: 10.11889/j.0253-3219.2017.hjs.40.100601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Accident analyses of station blackout for TMSR-SF2

XU Bo1,2, ZOU Yang1, SUN Qiang1, YU Xiaohan1   

  1. 1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China;
    2. University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2017-04-24 Revised:2017-05-03 Online:2017-10-10 Published:2017-09-29
  • Supported by:
    Supported by Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA0201002), the Frontier Science Key Program of Chinese Academy of Sciences (No.QYZDY-SSW-JSC016)

Abstract: Background: Thorium fluoride salt reactor-solid fuel 2 (TMSR-SF2) is a small module reactor (SMR) based on the experimental prototype SF1. Its concept design combines many outstanding characteristics from fluoride high temperature reactor (FHR), and brings in or enhances many more attractive features inspired from the small module idea. Purpose: This study aims to evaluate its operation performance and assess the safety limits during postulated transients. Methods: A preliminary analysis of station blackout (SBO) in SF2 is presented by using RELAP5/MOD4.0 code, relative hydraulic components have been equivalently modeled. Results: Modification result shows that an immediate safety shutdown can be obtained and guaranteed by strong thermal inertia while passive safety system based on natural circulation can maintain long term cooling of the reactor core and guarantee no server consequences and sufficient redundancy. Several postulated initiating events and sensitivity analyses covering several reactivity coefficients are also performed to reveal their influence degree and tendency on final results. Conclusion: The conclusion is that the shutdown system is crucially responsible for short-term safety while a long-term reactor cooling has to depend on the direct reactor auxiliary cooling system (DRACS).

Key words: TMSR, Small module reactor, Station blackout, Accident analysis, RELAP5

CLC Number: 

  • TL364+.4