Calculations of fuel burn-up and radionuclide inventory in the syrian miniature neutron source reactor using the WIMSD4 code |
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| Affiliation: | 1. Department of Engineering, University of Cambridge, United Kingdom;2. Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Republic of Korea;1. Institute of Geological Sciences, National Academy of Sciences of Ukraine, Gonchara 55B, 01 601 Kyiv, Ukraine;2. National Museum of Natural History, National Academy of Sciences of Ukraine, 15 Bohdan Khmelnitsky, Kyiv 01 601, Ukraine;3. Department of Geoecology and Palaeogeography, Maria Curie-Sk?odowska University, Al. Kra?nicka 2 cd, 20-718 Lublin, Poland;4. Institute of Geography, Department of Geomorphology and Quaternary Geology, University of Gdańsk, ul. Ba?yńskiego 4, 80-950 Gdańsk, Poland;5. Department of Geomorphology and Palaeogeography, Ivan Franko National University, Doroshenka 41, 79000 Lviv, Ukraine;1. Department of Engineering, University of Cambridge, CB2 1PZ Cambridge, United Kingdom;2. Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701, Republic of Korea |
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| Abstract: | Calculations of the fuel burn up and radionuclide inventory in the Miniature Neutron Source Reactor after 10 years (the reactor core expected life) of the reactor operating time are presented in this paper. The WIMSD4 code is used to generate the fuel group constants and the infinite multiplication factor versus the reactor operating time for 10, 20, and 30 kW operating power levels. The amounts of uranium burnt up and plutonium produced in the reactor core, the concentrations and radioactivities of the most important fission product and actinide radionuclides accumulated in the reactor core, and the total radioactivity of the reactor core are calculated using the WIMSD4 code as well. |
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