An improved porous media model for nuclear reactor analysis

查看全文 作　　者：Roozbeh [1]Vadi;Kamran [1]Sepanloo

机构地区：[1]Schools of Nuclear Safety Research and Radiation Protection,Nuclear Science and Technology Research Institute,End of North Karegar Ave.,P.O.Box:14359-836,Tehran,Iran

出　　处：《Nuclear Science and Techniques》索引2016年第27卷第1期,共24页

摘　　要：In this study, two modifications are proposed to mitigate drawbacks of the conventional approach of using the ‘‘Porous Media Model''(PMM) for nuclear reactor analysis. In the conventional approach, whole reactor core simplifies to a single porous medium and also, the resistance coefficients that are essential to using this model are constant values. These conditions impose significant errors and restrict the applications of the model for many cases,including accident analysis. In this article, the procedures for calculating the coefficients are modified by introducing a practical algorithm. Using this algorithm will result in obtaining each coefficient as a function of mass flow rate.Furthermore, the method of applying these coefficients to the reactor core is modified by dividing the core into several porous media instead of one. In this method, each porous medium comprises a single fuel assembly. PMM with these two modifications is termed ‘‘multi-region PMM'' in this study. Then, the multi-region PMM is introduced to a new CFD-based thermo-hydraulic code that is specifically devised for combining with neutronic codes.The CITVAP code, which solves multi-group diffusion equations, is the selected as the neutronic part for this study. The resulting coupled code is used for simulation of natural circulation in a MTR. A new semi-analytic method,based on steady-state CFD analysis is developed to verify the results of this case. Results demonstrate considerable improvement, compared to the conventional approach. 关键词：多孔介质模型模型分析反应器传统方法应用程序流体力学分析稳态计算 PMM

相关文献

参考文献（39）
引证文献（1）
耦合文献（0）

参考文献(39)

引证文献(1)

互联网出版许可证新出网证(渝)字10号全国400电话 - 免长途话费

An improved porous media model for nuclear reactor analysis

参考文献(39)

引证文献(1)

用户提示