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AbstractAbstract
[en] Although many thermal-hydraulic experiments have been performed in Korea, their experimental data are not systematically managed and effectively used for nuclear power plant design or research, for example, validating MARS code. So, in order to collect experimental data and assess the reliabilities of them, the project named 'Assessment of Thermal-hydraulic Experiment Database and Improvement of MARS Code' is underway. Last year, 2007, explorations on what experiments were performed and where they were performed in have been completed and procedures used to evaluate the reliability and usefulness of experiments were developed. In this year, second year, thermalhydraulic database system will be established and simulation using MARS code will be performed. Next year, detailed comparisons experimental data with MARS code calculation results will be conducted and, as an ultimate goal, suggestions on improvement of MARS code will be discussed. As a part of the project, the condensation experiments performed in POSTECH were investigated. Raw data, papers and reports were collected and analyzed. To assess MARS capacity on condensation, experimental data were compared with MARS code predictions. In this paper, experiment and MARS modeling are briefly described and comparison results are presented
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Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; May 2008; [2 p.]; 2008 spring meeting of the KNS; Kyeongju (Korea, Republic of); 29-30 May 2008; Available from KNS, Daejeon (KR); 3 refs, 6 figs
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
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