Please use this identifier to cite or link to this item: http://bura.brunel.ac.uk/handle/2438/26321
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dc.contributor.authorPoškas, R-
dc.contributor.authorRačkaitis, K-
dc.contributor.authorPoškas, P-
dc.contributor.authorJouhara, H-
dc.date.accessioned2023-04-26T17:32:06Z-
dc.date.available2023-04-26T17:32:06Z-
dc.date.issued2023-04-18-
dc.identifierORCID iDs:Kęstutis Račkaitis https://orcid.org/0000-0003-0353-9100; Hussam Jouhara https://orcid.org/0000-0002-6910-6116.-
dc.identifier.citationPoškas, R. et al. (2023) 'Modelling of the fire impact on CONSTOR RBMK-1500 cask thermal behavior in the open interim storage site', Nuclear Engineering and Technology, 55 (7), pp. 2604 - 2612. doi: 10.1016/j.net.2023.04.026.en_US
dc.identifier.urihttps://bura.brunel.ac.uk/handle/2438/26321-
dc.description.abstractCopyright © 2023 Korean Nuclear Society, Spent nuclear fuel and long-lived radioactive waste must be carefully handled before disposing them off to a geological repository. After the pre-storage period in water pools, spent nuclear fuel is stored in casks, which are widely used for interim storage. Interim storage in casks is very important part in the whole cycle of nuclear energy generation. This paper presents the results of the numerical study that was performed to evaluate the thermal behavior of a metal-concrete CONSTOR RBMK–1500 cask loaded with spent nuclear fuel and placed in an open type interim storage facility which is under fire conditions (steady-state, fire, post-fire). The modelling was performed using the ANSYS Fluent code. Also, a local sensitivity analysis of thermal parameters on temperature variation was performed. The analysis demonstrated that the maximum increase in the fuel load temperatures is about 10 °C and 8 °C for 30 min 800 °C and 60 min 600 °C fires respectively. Therefore, during the fire and the post-fire periods, the fuel load temperatures did not exceed the 300°C limiting temperature set for an RBMK SNF cladding for long-term storage. This ensures that fire accident does not cause overheating of fuel rods in a cask.en_US
dc.format.extent2604 - 2612-
dc.format.mediumElectronic-
dc.languageEnglish-
dc.language.isoen_USen_US
dc.publisherElsevier on behalf of Korean Nuclear Societyen_US
dc.rightsCopyright © 2023 Korean Nuclear Society, Published by Elsevier Korea LLC. under a Creative Commons license (https://creativecommons.org/licenses/by-nc-nd/4.0/).-
dc.rights.urihttps://creativecommons.org/licenses/by-nc-nd/4.0/-
dc.subjectRBMKen_US
dc.subject1500 spent nuclear fuelen_US
dc.subjectinterim storageen_US
dc.subjectmetal-concrete CONSTOR casken_US
dc.subjectthermal analysisen_US
dc.subjectfire conditionsen_US
dc.titleModelling of the fire impact on CONSTOR RBMK-1500 cask thermal behavior in the open interim storage siteen_US
dc.typeArticleen_US
dc.identifier.doihttps://doi.org/10.1016/j.net.2023.04.026-
dc.relation.isPartOfNuclear Engineering and Technology-
pubs.issueIn Press, Pre-proof-
pubs.issue7-
pubs.publication-statusPublished-
pubs.volume55-
dc.identifier.eissn1738-5733-
dc.rights.holderKorean Nuclear Society and the author(s).-
Appears in Collections:Dept of Mechanical and Aerospace Engineering Research Papers

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