Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (4): 40601-040601.doi: 10.11889/j.0253-3219.2017.hjs.40.040601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Preliminaryresearch of safety analysis for 10-MW thorium-basedmolten salt reactor-solid fuel

ZUO Jiaxu, GAO Xinli, LI Chaojun, SONG Wei, WANG Kunpeng, LIU Qiaofeng, JING Jianping, ZHANG Chunming   

  1. Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing 100082, China
  • Received:2016-11-11 Revised:2016-12-20 Online:2017-04-10 Published:2017-04-07
  • Supported by:

    Supported by National Natural Science Foundation of China (No.11505076), Strategic Priority Program of Chinese Academy of Sciences(No.XDA02050500)

Abstract:

Background: ThoriumMolten Salt Reactor (TMSR) project is one of the Strategic Priority Programprojects of Chinese Academy of Sciences. Based on the design of 10-MWThermal Molten Salt Reactor-Solid Fuel (TMSR-SF), the preliminary study on safety analysis of TMSR about the key technology are done. Purpose:This study aims to prepare the technology and requirements for TMSR-SF safety review, and show the guidance and support to the design. Methods:The study includesfour areas: core nuclear design safety limits, accident analysis and acceptance criteria, the source term and the review methods and acceptance criteria, probabilistic riskassessment (PRA) methods and initiating events.The safety review methods of other type reactors have been studied and compared. The key parameters and important regulations have been summary. From review and summary of the high temperature gas coolant reactor and sodium cooled fast reactor, based on the logic diagram methods, the PRA framework of TMSR-SF and initiating events list are discussed. The Monte Carlo and other methods and models are used to calculate the key core nuclear design safety parameters limits of TMSR-SF. The accident list and classification are studied and discussed from computational fluid dynamics (CFD) calculation.Results:The core design of TMSR-SF has sufficient negative reactivity coefficientsunder operating conditions.The temperature limit could reference high temperature gas cooled reactor and could be set to 1495 ·C. The shutdown margin should not be less than 0.2 for TMSR-SF.Conclusion:The preliminary accident type and accident event list of design basis have been setup, and the initialingevents listhas been discussed.The study will support the safety review and safety design of TMSR-SF.

Key words: TMSR-SF1, Safety analysis, Core design, Accident analysis, Source term, PRA

CLC Number: 

  • TL99