Персона: Слободчук, Виктор Иванович
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Институт ядерной физики и технологий
Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.
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Виктор Иванович
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- ПубликацияТолько метаданныеTemperature conditions in the RBMK spent fuel pool in the event of disturbances in its cooling mode(2021) Hakobyan, D. A.; Slobodchuk, V. I.; Слободчук, Виктор Иванович
- ПубликацияТолько метаданныеTEMPERATURE CONDITIONS in the RBMK SPENT FUEL STORAGE POOL in the EVENT of DISTURBANCES in ITS COOLING MODE ТЕМПЕРАТУРНЫИ РЕЖИМ В БАССЕИНЕ ВЫДЕРЖКИ РБМК ПРИ НАРУШЕНИИ УСЛОВИИ ЕГО ОХЛАЖДЕНИЯ(2020) Slobodchuk, V. I.; Hakobyan, D. A.; Слободчук, Виктор Иванович© 2020 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.The problems of reprocessing and long-term storage of spent nuclear fuel (SNF) at nuclear power plants with RBMK-type reactors have not been fully resolved so far. As a result, nuclear power plants are forced to search for new options of temporary storage of SNF. One of the possible temporary solutions to the problem is compacted SNF storage in the reactor spent fuel storage pool (SFSP). As the number of spent fuel assemblies (SFA) in the SFSP increases, a greater amount of heat is released. In addition, it is necessary to take into account the fact that provision should be made for some additional storage space in the pool where fuel assemblies can be placed in an emergency situation. The paper presents the results of a numerical simulation of the temperature regime in the spent fuel storage pool both for storage of compacted SFAs and for emergency unloading of fuel assemblies. Several types of disturbances in the normal SFSP cooling mode are considered, including partial loss of cooling water and uncovering of SFA. The simulation was performed using the ANSYS CFX code. The time it takes for the water to reach the boiling point is estimated, as well as the time over which the fuel cladding is heated to 650°C. The most critical conditions are observed in the compartment for emergency unloading of fuel assemblies. The results obtained make it possible to estimate the time that personnel have to restore the cooling mode of the spent fuel storage pool before the maximum water and SFA temperature is reached.