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Accident tolerant fuels to replace uranium dioxide

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dc.contributor.authorAlhmoud, A. Z.
dc.contributor.authorKruglov, V. B.
dc.contributor.authorKruglov, A. B.
dc.contributor.authorКруглов, Александр Борисович
dc.date.accessioned2024-11-27T11:02:55Z
dc.date.available2024-11-27T11:02:55Z
dc.date.issued2020
dc.description.abstract© 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.
dc.identifier.citationAlhmoud, A. Z. Accident tolerant fuels to replace uranium dioxide / Alhmoud, A.Z., Kruglov, V.B., Kruglov, A.B. // Journal of Physics: Conference Series. - 2020. - 1679. - № 2. - 10.1088/1742-6596/1679/2/022063
dc.identifier.doi10.1088/1742-6596/1679/2/022063
dc.identifier.urihttps://www.doi.org/10.1088/1742-6596/1679/2/022063
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85097646126&origin=resultslist
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/22732
dc.relation.ispartofJournal of Physics: Conference Series
dc.titleAccident tolerant fuels to replace uranium dioxide
dc.typeConference Paper
dspace.entity.typePublication
oaire.citation.issue2
oaire.citation.volume1679
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