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Riemke, R.A., Davis, C.B. and Schultz, R.R. (2006) RELAP5-3D code includes ATHNEA features and Models. The 14th International Conference on Nuclear Engineering, Miami, 17-20 July 2006, 1-11.

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  • 标题: RETRAN-3D和RELAP5程序壁面换热模型比较研究Comparative Study of the Wall Heat Transfer Model between the RETRAN-3D and RELAP5 Code

    作者: 刘建阁, 朱建敏, 陈军, 傅先刚

    关键字: RETRAN-3D程序, RELAP5程序, 壁面换热关系式, 临界热流密度RETRAN-3D Code, RELAP5 Code, Wall Heat Transfer Correlation, Critical Heat Flux

    期刊名称: 《Nuclear Science and Technology》, Vol.3 No.3, 2015-07-09

    摘要: 本文调研总结了RETRAN-3D和RELAP5程序的特点,分析了两个程序选择壁面换热模型的根本出发点,比较了两个程序所选用的壁面换热模型和临界热流密度计算方法,比较了水物性表的不同,简要分析了两者之间的差异。结果表明:两个程序因场方程模型构造的数量和解决核系统热工水力问题的侧重点不同,因而,在壁面换热模型的选择使用上存在着明显的差异;两个程序计算临界热流密度的选择不同,RETRAN-3D程序采用了多个可供选择的经验公式,RELAP5程序主要采用表格法;使用程序时,必须先进行程序适用性评估,在程序许可的使用范围进行建模分析,并对壁面换热关系式、临界热流密度和水蒸气物性参数的不确定性进行研究。The characteristics of the RETRAN-3D and the RELAP5 code are summarized. The selection origin of the wall heat transfer in the two codes is briefly analyzed. The heat transfer model and the critical heat flux model are listed and compared. The differences of the water-steam table are also in-troduced. The results show that: there are clearly differences in the choosing wall heat transfer correlations, as the different number of field equations and the keystone of solving the nuclear thermal-hydraulic system behavior are different. Two codes use different method to calculate the critical heat flux: the RETRAN-3D code adopts many experiential correlations to obtain the critical heat flux and the RELAP5 code adopts the look up table method. It must firstly carry out the code capability assessment and use the code in its applicability scopes. It is necessary to study the un-certainty of wall heat transfer correlations, critical heat flux and water property.

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