Персона: Круглов, Александр Борисович
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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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Руководитель научной группы "Теплофизические свойства материалов ядерной техники"
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Круглов
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Александр Борисович
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- ПубликацияТолько метаданныеThermal conductivity of lead in the temperature range of 350–1000 °C(2022) Kruglov, A. B.; Rachkov, V. I.; Merinov, I. G.; Kharitonov, V. S.; Paredes, L. P.; Круглов, Александр Борисович; Рачков, Валерий Иванович; Меринов, Игорь Геннадьевич; Харитонов, Владимир СтепановичThe article presents the results of measuring the coefficient of thermal conductivity of lead in the temperature range of 350–1000 °C using the pulse heating method. The methodology of processing experimental data is described. The estimates of the experimental data error are given. The difference in the content of impurities in the lead samples is shown to have an in significant effect on the thermal conductivity coefficient of the lead melt. The deviation of the experimental data on the thermal conductivity of lead from the proposed approximating function does not exceed ±2 %. The obtained data are compared with the known recommended dependences for calculating the thermal conductivity coefficient of lead. © 2022, A.B. Kruglov, V.I. Rachkov, I.G. Merinov, V.S. Kharitonov, and L.P. Paredes.
- ПубликацияТолько метаданныеDifferent-sized porosity and thermal conductivity of oxide layers formed by plasma-electrolytic oxidation on the AlSi12Mg silumin Разноразмерная пористость и теплопроводность оксидных слоев, сформированных плазменно-электролитическим оксидированием на силумине АК12Д(2022) Ivashin, P. V.; Криштал, М. М.; Полунин, А. В.; Твердохлебов, А. Я.; Дударева, Н. Ю.; Kruglov, A. B.; Круглов, Александр Борисович
- ПубликацияТолько метаданныеDependence of the thermophysical properties of alloys of the Fe-Cr-Al-Si system on the composition and temperature(2022) Kruglov, A. B.; Savelyev, M.; Tarasov, B. A.; Круглов, Александр Борисович; Савельев, Максим Дмитриевич; Тарасов, Борис Александрович
- ПубликацияТолько метаданныеThermal conductivity of Pb-Na and Pb-Bi-Na alloys in the temperature range of 350–800 °C(2023) Kruglov, A. B.; Konovalov, I. I.; Tarasov, B. A.; Kharitonov, V. S.; Paredes, L. P.; Круглов, Александр Борисович; Коновалов, Игорь Иванович; Тарасов, Борис Александрович; Харитонов, Владимир Степанович
- ПубликацияТолько метаданныеInvestigating the contact thermal resistances of lead in a heat conducting sublayer(2024) Kruglov, A. B.; Rachkov, V. I.; Merinov, I. G.; Kharitonov, V. S.; Paredes, L. P.; Круглов, Александр Борисович; Рачков, Валерий Иванович; Меринов, Игорь Геннадьевич; Харитонов, Владимир Степанович
- ПубликацияОткрытый доступTolerant fuel for VVER reactors(2020) Alhmoud, A. Z.; Kruglov, V. B.; Kruglov, A. B.; Tanash, H. A.; Круглов, Александр Борисович© Published under licence by IOP Publishing Ltd.The main factor of destruction of fuel rods in accidents with loss of coolant is associated with the vapor-zirconium reaction occurring between the fuel rod shell and the coolant (water). Improving the reliability of fuel cells can be obtained by modifying or replacing the fuel shell, materials that do not interact with the coolant during normal operation and in emergencies. The loss of coolant accident is a design-basis accident in light water reactors. The postulated accident requires an analysis of the double guillotine break in a main primary coolant pipe, which allows the coolant to freely discharge out of the primary system into the containment of the building. In the present work, the heat stored in the active zone of the reactor, the heat capacity of the fuel and the shell temperatures are determined for ATF materials U-10Mo and U3Si2. The calculated values are compared with the usually used fuel UO2. The results showed beneficial effect of using ATF materials. The above quantities are decreased dramatically for ATF, promising to replace UO2 with ATF fuels. This reduces the probabilities of accidents and oxidation in the nuclear reactors. The calculations are done for nuclear power plant, type VVER-1200.
- ПубликацияОткрытый доступMethod for determining of the coatings thermophysical properties formed by the microarc oxidation(2019) Dudareva, N.; Gallyamova, R.; Kruglov, A.; Круглов, Александр БорисовичIn this work are determined the thermophysical parameters (coefficient of thermal conductivity, thermal diffusivity and heat capacity) of a coating formed by the microarc oxidation (MAO) method on an aluminum alloy AK12D. A method for determining the thermal properties of the MAO layers was developed and verified. The technique is based on measuring the thermal conductivity of the layer by pulsed laser heating and calculating its heat capacity and density based on the data of layer-by-layer phase analysis taking into account the volume porosity. The method allows to calculate the thermophysical parameters whose values differ from the experimental no more than 2.2% in thermal conductivity and no more than 7.0% for heat capacity. In accordance with the proposed method, it was found that the MAO layer on AK12D alloy has a low thermal conductivity of similar to 1.57 W/(m.K) at 100 degrees C.
- ПубликацияОткрытый доступAccident tolerant fuels to replace uranium dioxide(2020) Alhmoud, A. Z.; Kruglov, V. B.; Kruglov, A. B.; Круглов, Александр Борисович© Published under licence by IOP Publishing Ltd.The thermal conductivities for the traditional fuel UO2 and for the Accident Tolerant Fuel (uranium Molybdenum alloy, U-10Mo and uranium silicide, U3Si2) are calculated and compared. Then the temperature distributions on these core reactor, namely on the surface of the rod and in the center line of the rod were determined. The calculation is carried out using MATHCAD program. The calculations showed enhancement of thermal conductivity of the Accident Tolerant Fuel as they increased linearly with increasing temperature, and reduction of their center line temperatures of the rods. Beside, their steep thermal gradient, which may reduce the induced heat stresses in the core of the reactor.