Nuclear Techniques ›› 2014, Vol. 37 ›› Issue (03): 30605-030605.doi: 10.11889/j.0253-3219.2014.hjs.37.030605


Development and test of interphase friction model for reactor thermal-hydraulic safety analysis

CAI Yi1 LIN Meng1 ZHANG Hao2 YANG Yanhua2   

  1. 1(Institute of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China) 2(State Nuclear Power Software Development Center, Beijing 100029, China)
  • Received:2013-12-25 Revised:2014-01-25 Online:2014-03-10 Published:2014-03-14


Background: In order to change the status that nuclear power software technology lags behind the foreign countries, the thermal-hydraulic safety analysis program COSINE is being developed. Purpose: To complete the solution of the hydraulics equation, a fully considered model of detailed vapor and liquid interphase friction was proposed. Methods: With reference to some mature interphase friction models, we developed the FORTRAN program for the model and designed appropriate numerical routines to test the model. And the RELAP5/Mod3.2 was applied to results comparison of the rationality and accuracy of the model. Results and Conclusion: The results show that the model is valid and the program can run normally.

Key words: Thermal hydraulics analysis, Interphase friction, Model development, Program test