Prediction of Fuel Performance and Fission Gas Release Behavior during Normal Operation of the High Temperature Engineering Test Reactor by JAERI and FZJ Modeling Approach
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概要
- 論文の詳細を見る
In high temperature gas-cooled reactors (HTGRs), coated fuel particles are employed as fuel to permit high outlet coolant temperature. The essential feature of HTGRs is the role of the coated fuel particles acting as tiny containment and the principal barrier against radionuclide release under any operational and accident condition. For a safe operation of the High Temperature Engineering Test Reactor (HTTR), the continuous and reliable measurement of the coolant activity is required to allow an evaluation of the fuel performance and the radiological assessment of the plant during normal operation conditions. Since fission gases do not plateout on the inner surface of the primary cooling system, their concentrations in the primary coolant reflect the core-average through-coatings failure fraction and the fuel matrix contamination fraction. The main purpose of this report was to give a prediction of the fuel performance and fission product behavior in the HTTR under normal operating conditions by applying the calculation models as used at Japan Atomic Energy Research Institute and Research Center Juelich (FZJ), Germany, and to compare the results and methodologies. In the prediction of core average failure fraction, JAERI model gave much earlier failure and about two times larger than FZJ model. In the fission gas release prediction, FZJ model showed later increase of fractional release than JAERI model and rapidly increased towards the end of the operation.
- 社団法人 日本原子力学会の論文
- 2001-06-25
著者
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Sumita J
Japan Atomic Energy Res. Inst. Ibaraki
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Sawa K
Japan Atomic Energy Res. Inst. Chiba
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Sawa Kazuhiro
Department Of Electrical Engineering Faculty Of Engineering Mie University
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UETA Shouhei
Department of HTTR Project, Oarai Research Establishment, Japan Atomic Energy Research Institute
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SUMITA Junya
Department of HTTR Project, Oarai Research Establishment, Japan Atomic Energy Research Institute
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VERFONDERN Karl
Institute for Safety Research and Reactor Technology, Research Center Juelich, ISR-I
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Ueta S
Japan Atomic Energy Res. Inst. Ibaraki
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Verfondern Karl
Institute For Safety Research And Reactor Technology Research Center Juelich Isr-i
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