Journal of University of Science and Technology of China ›› 2020, Vol. 50 ›› Issue (4): 428-435.DOI: 10.3969/j.issn.0253-2778.2020.04.006

• Original Paper • Previous Articles     Next Articles

Simulating method of sodium-water reaction accident in steam generator of sodium-cooled fast reactor

XIANG Yang, TAN Chao, CHEN Yunlong, ZHU Jiayin, YU Shuwen, ZHAO Pinghui   

  1. 1.School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 260026, China; 2.Research Institute of Nuclear Power Operation,China National Nuclear Corporation, Wuhan 430074, China
  • Received:2019-04-01 Revised:2019-05-22 Accepted:2019-05-22 Online:2020-04-30 Published:2019-05-22

Abstract: The simulation of sodium-water reaction accident is the difficulty in the development of the simulating system of sodium cooled reactor. In order to solve this problem, a simulation program of sodium-water reaction accident was designed based on the mathematical physical equation of sodium-water reaction accident caused by water leakage in heat transfer tube of sodium-cooled fast reactor steam generator. Based on SimTherm thermal-hydraulic simulation program and the structure of sodium-cooled fast reactor, a second-circuit model of sodium-cooled fast reactor was designed for the study of sodium-water reaction accidents. By coupling the simulation program of sodium-water reaction accident with SimTherm, the simulation of sodium-water reaction accident was realized, which provides a new idea for the development of sodium-cooled fast reactor simulator.

Key words: numerical reactor, sodium-water reaction accident, security analysis of nuclear reactor, sodium cooled fast reactor

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