Nuclear Science and Techniques ›› 2019, Vol. 42 ›› Issue (1): 10603-010603.doi: 10.11889/j.0253-3219.2019.hjs.42.010603

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Study on hydrogen migration behavior in small leakage accident of steam generator of sodium-cooled fast reactor

Xinjie DENG,Xuewu CAO()   

  1. 1. School of Mechanical and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
  • Received:2018-11-08 Revised:2018-12-13 Online:2019-01-10 Published:2019-01-25
  • Contact: Xuewu CAO
  • Supported by:
    Supported by National Natural Science Foundation of China (No.11675104) and National Science and Technology Major Project (No.2015ZX06004003-001)

Abstract: Background

Sodium-cooled fast reactors adopt sodium-sodium-water/steam three-loop heat transfer mode, heat exchange between the sodium in the secondary circuit and the water/steam in the third circuit is achieved by the steam generator. Even tiny crack of the heat-transfer tube in the steam generator may lead to sodium water reaction.


This study aims at hydrogen migration behavior in sodium-cooled fast reactor so as to effectively curb the expansion of small leakage accident by detecting the occurrence of sodium-water reaction in time.


First of all, a one-dimensional calculation model of small leakage sodium-water reaction in the secondary loop of sodium-cooled fast reactor is established. Then a one-dimensional analysis program is written in Fortran language, which can calculate the generation and migration of hydrogen gas in the sodium water reaction of small leakage. Meanwhile, the calculated results are compared with those of a reference. Finally, in the case where a heat transfer tube of the steam generator is broken, the effects of leakage rate and sodium temperature on the migration of hydrogen in the secondary sodium are analyzed.[Results &


Analysis results show that the rate of hydrogen concentration change in the secondary circuit can be used to monitor the occurrence of minor leakage accidents, hence provide a reference for the arrangement of the small leakage detection system in the secondary loop of sodium-cooled fast reactor.

Key words: Sodium-cooled fast reactor, Small leak, Sodium-water reaction, Hydrogen migration

CLC Number: 

  • TL36