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Please use this identifier to cite or link to this item: http://hdl.handle.net/1843/56840
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dc.creatorFernando Pereira Fariapt_BR
dc.creatorJean Anderson Dias Salomépt_BR
dc.creatorCristiane Vianapt_BR
dc.creatorFabiano Cardoso da Silvapt_BR
dc.creatorCarlos Eduardo Velasquez Cabrerapt_BR
dc.creatorClaubia Pereira Bezerra Limapt_BR
dc.date.accessioned2023-07-21T17:20:26Z-
dc.date.available2023-07-21T17:20:26Z-
dc.date.issued2016-
dc.citation.issue5th International Atalante Conference on Nuclear Chemistry For Sustainable Fuel Cyclespt_BR
dc.citation.spage386pt_BR
dc.citation.epage393pt_BR
dc.identifier.doihttps://doi.org/10.1016/j.proche.2016.10.054pt_BR
dc.identifier.issn1876-6196pt_BR
dc.identifier.urihttp://hdl.handle.net/1843/56840-
dc.description.resumoIn the first part, Pressurized Water Reactor (PWR), Very High-Temperature Reactor (VHTR) and Accelerator-Driven Subcritical Reactor System (ADS) spent fuels (SF) were evaluated to the thermal of the spent fuel pool (SFP) without an external cooling system. The goal is to compare the water boiling time of the pool storing different types of spent nuclear fuels. This study used the software Ansys Workbench 16.2 - student version. For the VHTR, two types of fuel were analyzed: (Th,TRU)O2 and UO2. This part of the studies were performed for wet storage condition using a single type of SF and decay heat values at times t=0 and t=10 years after the reactor discharge. The Ansys CFX module was used and the results show that the time that water takes to reach the boiling point varies from 2.4 minutes for the case of VHTR-(Th,TRU)O2 SF at time t=0 year after reactor discharge until 32.4 hours for the case of PWR SF at time t=10 years after the discharge reactor. The second part of this work consists of modeling a geological repository. Firstly, the temperature evaluation of the spent fuel from a PWR was analyzed. A PWR canister was simulated using the Ansys transient thermal module. Then the temperature of canister could be computed during the time spent on a portion of a geological repository. The mean temperature on the canister surface increased during the first nine years, reaching a plateau at 35.5°C between the tenth and twentieth years after the geological disposal. The idea is to extend this study for the other systems analyzed in the first part. The idea is to include in the study, the spent fuels from VHTR and ADS and to compare the canister behavior using different spent fuels.pt_BR
dc.languageporpt_BR
dc.publisherUniversidade Federal de Minas Geraispt_BR
dc.publisher.countryBrasilpt_BR
dc.publisher.departmentENG - DEPARTAMENTO DE ENGENHARIA NUCLEARpt_BR
dc.publisher.initialsUFMGpt_BR
dc.relation.ispartofInternational atalante conference on nuclear chemistry for sustainable fuel cyclespt_BR
dc.rightsAcesso Abertopt_BR
dc.subjectThermal analysispt_BR
dc.subjectAnsys CFXpt_BR
dc.subjectAnsys transient thermalpt_BR
dc.subjectSpent fuelspt_BR
dc.subjectSpent fuel poolpt_BR
dc.subjectGeological repositorypt_BR
dc.subject.otherAnalise termicapt_BR
dc.subject.otherCombustiveispt_BR
dc.titleThermal Analysis of Spent Nuclear Fuels Repositorypt_BR
dc.typeArtigo de Eventopt_BR
dc.url.externahttps://www.sciencedirect.com/science/article/pii/S1876619616300961?via%3Dihubpt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-2960-3150pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0001-5999-9961pt_BR
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