Thermal analysis of IRT-T reactor fuel elements
| Autor: | A. Naymushin, Yu Chertkov, M.N. Anikin, I.I. Lebedev |
|---|---|
| Jazyk: | angličtina |
| Rok vydání: | 2015 |
| Předmět: |
Engineering
теплофизические расчеты business.industry Nuclear engineering Mechanical engineering Thermal power station ИРТ-Т Cladding (fiber optics) реакторы Coolant Power rating Nuclear reactor core топливные элементы Research reactor Physics::Chemical Physics Thermal analysis business исследовательские реакторы термический анализ Nucleate boiling |
| Popis: | The article describes the method and results of thermo-physical calculations of IRT-T reactor core. Heat fluxes, temperatures of cladding, fuel meat and coolant were calculated for height of core, azimuth directions of FA and each fuel elements in FA. Average calculated values of uniformity factor of energy release distribution for height of fuel assemblies were shown in this research. Onset nucleate boiling temperature and ONB-ratio were calculated. Shows that temperature regimes of fuel elements at rated power of the reactor keep within limit values and meet safety requirements. Obtained results could be applied at feasibility study of increasing thermal power of IRT-T research reactor to 12 MW level. |
| Databáze: | OpenAIRE |
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