Thermal Analysis of Spent Nuclear Fuels Repository
| dc.creator | Fernando Pereira Faria | |
| dc.creator | Jean Anderson Dias Salomé | |
| dc.creator | Cristiane Viana | |
| dc.creator | Fabiano Cardoso da Silva | |
| dc.creator | Carlos Eduardo Velasquez Cabrera | |
| dc.creator | Claubia Pereira Bezerra Lima | |
| dc.date.accessioned | 2023-07-21T17:20:26Z | |
| dc.date.accessioned | 2025-09-09T00:45:02Z | |
| dc.date.available | 2023-07-21T17:20:26Z | |
| dc.date.issued | 2016 | |
| dc.identifier.doi | https://doi.org/10.1016/j.proche.2016.10.054 | |
| dc.identifier.issn | 1876-6196 | |
| dc.identifier.uri | https://hdl.handle.net/1843/56840 | |
| dc.language | por | |
| dc.publisher | Universidade Federal de Minas Gerais | |
| dc.relation.ispartof | International atalante conference on nuclear chemistry for sustainable fuel cycles | |
| dc.rights | Acesso Aberto | |
| dc.subject | Analise termica | |
| dc.subject | Combustiveis | |
| dc.subject.other | Thermal analysis | |
| dc.subject.other | Ansys CFX | |
| dc.subject.other | Ansys transient thermal | |
| dc.subject.other | Spent fuels | |
| dc.subject.other | Spent fuel pool | |
| dc.subject.other | Geological repository | |
| dc.title | Thermal Analysis of Spent Nuclear Fuels Repository | |
| dc.type | Artigo de evento | |
| local.citation.epage | 393 | |
| local.citation.issue | 5th International Atalante Conference on Nuclear Chemistry For Sustainable Fuel Cycles | |
| local.citation.spage | 386 | |
| local.description.resumo | In 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. | |
| local.identifier.orcid | https://orcid.org/0000-0002-2960-3150 | |
| local.identifier.orcid | https://orcid.org/0000-0001-5999-9961 | |
| local.publisher.country | Brasil | |
| local.publisher.department | ENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR | |
| local.publisher.initials | UFMG | |
| local.url.externa | https://www.sciencedirect.com/science/article/pii/S1876619616300961?via%3Dihub |