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

CAI Yi; LIN Meng; ZHANG Hao; YANG Yanhua

doi:10.11889/j.0253-3219.2014.hjs.37.030605

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

更新时间：2021-03-03

- Development and test of interphase friction model for reactor thermal-hydraulic safety analysis
- NUCLEAR TECHNIQUES Vol. 37, Issue 3, Article number: 030605(2014)
- 作者机构：
  
  1. 上海交通大学机械与动力工程学院,上海,200240
  2. 国家核电软件中心,北京,100029
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2014.hjs.37.030605
  CLC：
- Published：14 March 2014
- 稿件说明：
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CAI Yi, LIN Meng, ZHANG Hao, et al. Development and test of interphase friction model for reactor thermal-hydraulic safety analysis[J]. Nuclear techniques, 2014, 37(3): 030605
DOI：

CAI Yi, LIN Meng, ZHANG Hao, et al. Development and test of interphase friction model for reactor thermal-hydraulic safety analysis[J]. Nuclear techniques, 2014, 37(3): 030605 DOI： 10.11889/j.0253-3219.2014.hjs.37.030605.

摘要

本文在自主研发大型热工安全分析程序COSINE的背景下，以成熟热工水力模型为参考，开发了一个考虑全面分区详尽的汽液相间摩擦模型，编写调试了FORTRAN程序应用于该模型，并设计适当算例对该模型进行功能测试。通过对计算结果与RELAP5/Mod3.2程序的计算结果进行比较分析，模型的合理性与准确性得到了验证。

Abstract

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.Cited

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