Thermal hydraulic and safety analysis for core conversion (HEU–LEU) of Syrian Miniature Neutron Source Reactor |
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| Affiliation: | 1. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, China;2. State Nuclear Power Research Institute, Beijing 100029, China;1. Masaki Tech LLC, 1254 Chimiya-cho, Izumo-shi, Shimane 693-0033 Japan;2. Central Research Institute of Electric Power Industry (CRIEPI), 2-6-1 Nagasaka, Yokosuka-shi, Kanagawa 240-0196 Japan;3. Cooperative Major in Nuclear Energy, Waseda University, 3-4-1 Okubo, Shinjuku-ku, Tokyo 169-8555, Japan;1. Nuclear Engineering, University of Michigan, 2355 Bonisteel Blvd, Ann Arbor, MI, United States;2. School of Nuclear Science and Technology, Xian Jiaotong University, Xian 710049, China;3. Chemical Engineering, Brigham Young University, 350U Clyde Building, Provo, UT, United States;1. Key Laboratory of Thermo-Fluid Science and Engineering, Ministry of Education, School of Energy and Power Engineering, Xi''an Jiaotong University, Xi''an, Shaanxi 710049, PR China;2. Shanghai Marine Diesel Engine Research Institute, Shanghai 201108, PR China;1. National Center for Radiation Research and Technology, Atomic Energy Authority, P.O. box 8029 Nasr City, Cairo, Egypt;2. King Abdulaziz City for Science and Technology, National Center for Irradiation Technology, Riyadh, Saudi Arabia;1. Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan;2. Graduate School of Engineering, Kobe University, 1-1 Rokkodai, Nada-ku, Kobe-shi, Hyogo 657-8501, Japan |
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| Abstract: | The paper presents the behavior and properties analysis of the low enriched uranium fuel compared with the original high enriched uranium fuel. The MNSR reactor core was modeled with both fuel materials and the reactor behavior was studied during the steady state and abnormal conditions. The MERSAT code was used in the analysis. The steady state thermal hydraulic analysis results were compared with that obtained from the experimental results hold during commissioning the Syrian MNSR. Comparison with experimental data shows that the steady-state behavior of the HEU core was accurately predicted by the MERSAT code calculations. The validated model was then used to analyze LEU cores with two proposed UO2 fuel pin designs. With each LEU core, the steady state and 3.77 mk rod withdrawal transient were run and the results were compared with the available published data in the literatures for the low enriched uranium fuel core. The results reveal that the low enriched uranium fuel showed a good behavior and the peak clad temperatures remain well below the clad melting temperature during reactivity insertion accident. |
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