• Title/Summary/Keyword: PWRs

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Development of a Subchannel Analysis Code MATRA Applicable to PWRs and ALWRs

  • Yoo, Yeon-Jong;Hwang, Dae-Hyun;Sohn, Dong-Seong
    • Nuclear Engineering and Technology
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    • v.31 no.3
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    • pp.314-327
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    • 1999

  • A subchannel analysis code MATRA applicable to PWRs and ALWRs has been developed to be run on an IBM PC or HP WS based on the existing CDC CYBER mainframe version of COBRA-Rf-1. This MATRA code is a thermal-hydraulic analysis code based on the subchannel approach for calculating the enthalpy and How distribution in fuel assemblies and reactor cores for both steady-state and transient conditions. HATRA has been provided with an improved structure, various functions, and models to give more convenient user environment and to enhance the code accuracy. Among them, the pressure drop model has been improved to be applied to non-square-lattice rod arrays, and the models for the lateral transport between adjacent subchannels have been improved to enhance the accuracy in predicting two-phase flow phenomena. The predictions of MATRA were compared with the experimental data on the flow and enthalpy distribution in some sample rod-bundle cases to evaluate the performance of MATRA. All the results revealed that the predictions of MATRA were better than those of COBRA-IV-I.

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DEVELOPMENT OF THE SPACE CODE FOR NUCLEAR POWER PLANTS

  • Ha, Sang-Jun;Park, Chan-Eok;Kim, Kyung-Doo;Ban, Chang-Hwan
    • Nuclear Engineering and Technology
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    • v.43 no.1
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    • pp.45-62
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    • 2011

  • The Korean nuclear industry is developing a thermal-hydraulic analysis code for safety analysis of pressurized water reactors (PWRs). The new code is called the Safety and Performance Analysis Code for Nuclear Power Plants (SPACE). The SPACE code adopts advanced physical modeling of two-phase flows, mainly two-fluid three-field models which comprise gas, continuous liquid, and droplet fields and has the capability to simulate 3D effects by the use of structured and/or nonstructured meshes. The programming language for the SPACE code is C++ for object-oriented code architecture. The SPACE code will replace outdated vendor supplied codes and will be used for the safety analysis of operating PWRs and the design of advanced reactors. This paper describes the overall features of the SPACE code and shows the code assessment results for several conceptual and separate effect test problems.

  • https://doi.org/10.5516/NET.2011.43.1.045 인용 PDF KSCI