Analysis of the disposal of spent nuclear fuel in Brazil
Autor(a) principal: | |
---|---|
Data de Publicação: | 2021 |
Tipo de documento: | Tese |
Idioma: | eng |
Título da fonte: | Repositório Institucional da UFMG |
Texto Completo: | http://hdl.handle.net/1843/41268 https://orcid.org/0000-0002-4533-2362 |
Resumo: | The disposal of radioactive waste has been the subject of scientific research since the beginning of the nuclear industry. For high-level waste or spent fuel, the final disposal in deep geological repositories is the global scientific consensus. In this doctoral thesis, aspects related to the process of disposal of spent nuclear fuel (SNF) in Brazil were studied, from a purely academic point of view. The radioactive decay process releases thermal energy that is absorbed by the geological environment. However, some of the safety barrier components have a maximum operating temperature limit. Furthermore, the heat released can help the migration of fluids in the geosphere. As the heat transfer process is passive, the repository must be dimensioned so that the thermal limits are not exceeded during its operation. The simulation of heat transfer allows the determination of the smallest acceptable geometric dimensions of the repository for each type of SNF. Given the Brazilian Government's apparent interest in reprocessed nuclear fuels, the thermal behavior of two reprocessed fuels for the Angra 2 nuclear power plant, a Mixed Oxide (MOX) and a thorium-enriched reprocessed fuel was simulated. The MOX fuel can be disposed of in a repository after 50 years of its removal from the reactor. The spent fuel containing thorium, however, cannot be disposed of in a repository under the same conditions, since the maximum safe temperature would be exceeded. The dimensioning of the repository for the SNF is an important piece of information for the process of selecting areas with the potential to house a geological repository. With the application of a method based on geographic information systems and multi-criteria analysis for the selection of an area for the construction of a repository for the SNF, sites of interest were selected for further. Candidate sites have areas greater than the minimum areas estimated as necessary by the heat transfer simulation. As both the nuclear fuel cycle and the total number of nuclear power plants to be built in this century remain undefined, there is no estimate of back-end costs in Brazil. To estimate the costs associated with this phase of the nuclear fuel life cycle, strategic scenarios were created. These scenarios, together with the possible fuel cycles, were modeled in the energy planning tool MESSAGE to estimate the amount of SNF generated. Using stochastic methods, the most likely total cost was calculated. Values range from $12.84 billion to $83.71 billion depending on the scenario. With this range, it was estimated that the energy sale value should be between 40% and 60% higher than the current value charged to finance the SNF disposal activities. |
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Claubia Pereira Bezerra Limahttp://lattes.cnpq.br/1635197498453054Fernando Pereira de FariaAntonella Lombardi CostaPatrícia Amélia de Lima ReisMichel Melo OliveiraFlávia SchenatoFrancisco Javier Rioshttp://lattes.cnpq.br/2588322683897027Raoni Adão Salviano Jonusan2022-04-29T19:26:39Z2022-04-29T19:26:39Z2021-10-06http://hdl.handle.net/1843/41268https://orcid.org/0000-0002-4533-2362The disposal of radioactive waste has been the subject of scientific research since the beginning of the nuclear industry. For high-level waste or spent fuel, the final disposal in deep geological repositories is the global scientific consensus. In this doctoral thesis, aspects related to the process of disposal of spent nuclear fuel (SNF) in Brazil were studied, from a purely academic point of view. The radioactive decay process releases thermal energy that is absorbed by the geological environment. However, some of the safety barrier components have a maximum operating temperature limit. Furthermore, the heat released can help the migration of fluids in the geosphere. As the heat transfer process is passive, the repository must be dimensioned so that the thermal limits are not exceeded during its operation. The simulation of heat transfer allows the determination of the smallest acceptable geometric dimensions of the repository for each type of SNF. Given the Brazilian Government's apparent interest in reprocessed nuclear fuels, the thermal behavior of two reprocessed fuels for the Angra 2 nuclear power plant, a Mixed Oxide (MOX) and a thorium-enriched reprocessed fuel was simulated. The MOX fuel can be disposed of in a repository after 50 years of its removal from the reactor. The spent fuel containing thorium, however, cannot be disposed of in a repository under the same conditions, since the maximum safe temperature would be exceeded. The dimensioning of the repository for the SNF is an important piece of information for the process of selecting areas with the potential to house a geological repository. With the application of a method based on geographic information systems and multi-criteria analysis for the selection of an area for the construction of a repository for the SNF, sites of interest were selected for further. Candidate sites have areas greater than the minimum areas estimated as necessary by the heat transfer simulation. As both the nuclear fuel cycle and the total number of nuclear power plants to be built in this century remain undefined, there is no estimate of back-end costs in Brazil. To estimate the costs associated with this phase of the nuclear fuel life cycle, strategic scenarios were created. These scenarios, together with the possible fuel cycles, were modeled in the energy planning tool MESSAGE to estimate the amount of SNF generated. Using stochastic methods, the most likely total cost was calculated. Values range from $12.84 billion to $83.71 billion depending on the scenario. With this range, it was estimated that the energy sale value should be between 40% and 60% higher than the current value charged to finance the SNF disposal activities.O descarte de rejeitos radioativos tem sido objeto de pesquisas científicas desde o início da indústria nuclear. Para resíduos de alto nível ou combustível irradiado, a disposição final em depósitos geológicos profundos é o consenso científico global. Nesta tese de doutorado, foram estudados, de um ponto de vista puramente acadêmicos, aspectos relacionados ao processo de destinação do combustível nuclear usado (SNF) no Brasil. O processo de decaimento radioativo libera energia térmica que é absorvida pelo ambiente geológico. No entanto, alguns dos componentes da barreira de segurança têm um limite máximo de temperatura operacional. Além disso, o calor liberado pode facilitar a migração de fluidos na geosfera. Como o processo de transferência de calor é passivo, o repositório deve ser dimensionado de forma que os limites térmicos não sejam ultrapassados durante o seu funcionamento. A simulação da transferência de calor permite a determinação das dimensões geométricas mínimas aceitáveis para cada tipo de SNF. Dado o aparente interesse do governo brasileiro em combustíveis nucleares reprocessados, foi simulado o comportamento térmico de dois combustíveis reprocessados para a usina nuclear de Angra 2, um Óxido Misto (MOX) e um combustível reprocessado enriquecido com tório. O combustível MOX pode ser descartado em um repositório após 50 anos de sua remoção do reator. O combustível irradiado contendo tório, entretanto, não pode ser descartado em um repositório nas mesmas condições, uma vez que a temperatura máxima de segurança seria excedida. O dimensionamento do repositório para o SFN é uma informação importante para o processo de seleção de áreas com potencial para abrigar um repositório geológico. Com a aplicação de um método baseado em sistemas de informações geográficas e análise multicritério para seleção de área para construção de repositório do SNF, foram selecionados sítios de interesse para futuros estudos. Os locais candidatos têm áreas maiores do que as áreas mínimas estimadas como necessárias pela simulação de transferência de calor. Como tanto o ciclo do combustível nuclear quanto o número total de usinas nucleares a serem construídas neste século permanecem indefinidos, não há estimativa de custos do back-end no Brasil. Para estimar os custos associados a esta fase do ciclo de vida do combustível nuclear, foram criados cenários estratégicos. Esses cenários, juntamente com os possíveis ciclos de combustível, foram modelados na ferramenta de planejamento de energia MESSAGE para estimar a quantidade de SNF gerada. Usando métodos estocásticos, o custo total mais provável foi calculado. Os valores estão na faixa entre US $ 12,84 bilhões e US $ 83,71 bilhões dependendo do cenário. Com esses valores, estimou-se que o valor de venda de energia deveria ser entre 40% e 60% maior que o atual cobrado para financiar as atividades de descarte do SNF.CNPq - Conselho Nacional de Desenvolvimento Científico e TecnológicoFAPEMIG - Fundação de Amparo à Pesquisa do Estado de Minas GeraisCAPES - Coordenação de Aperfeiçoamento de Pessoal de Nível SuperiorengUniversidade Federal de Minas GeraisPrograma de Pós-Graduação em Ciências e Técnicas NuclearesUFMGBrasilENG - DEPARTAMENTO DE ENGENHARIA NUCLEARhttp://creativecommons.org/licenses/by-nc-nd/3.0/pt/info:eu-repo/semantics/openAccessEngenharia nuclearAnálise térmicaCombustíveis nuclearesResíduos radioativosSpent fuelDeep geological repositoryCost estimationThermal analysisSite selectionAnalysis of the disposal of spent nuclear fuel in BrazilAnálise da disposição do combustível nuclear irradiado no BrasilAnálisis de la disposición de combustible nuclear gastado en BrasilAnalyse du stockage du combustible nucléaire usé au Brésilinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/doctoralThesisreponame:Repositório Institucional da UFMGinstname:Universidade Federal de Minas Gerais (UFMG)instacron:UFMGORIGINALTese_Raoni_Adão(A).pdfTese_Raoni_Adão(A).pdfapplication/pdf15408906https://repositorio.ufmg.br/bitstream/1843/41268/1/Tese_Raoni_Ad%c3%a3o%28A%29.pdf83e47c591fae0d8669e369630c0a30a1MD51CC-LICENSElicense_rdflicense_rdfapplication/rdf+xml; charset=utf-8811https://repositorio.ufmg.br/bitstream/1843/41268/2/license_rdfcfd6801dba008cb6adbd9838b81582abMD52LICENSElicense.txtlicense.txttext/plain; charset=utf-82118https://repositorio.ufmg.br/bitstream/1843/41268/3/license.txtcda590c95a0b51b4d15f60c9642ca272MD531843/412682022-04-29 16:26:40.234oai:repositorio.ufmg.br:1843/41268TElDRU7Dh0EgREUgRElTVFJJQlVJw4fDg08gTsODTy1FWENMVVNJVkEgRE8gUkVQT1NJVMOTUklPIElOU1RJVFVDSU9OQUwgREEgVUZNRwoKQ29tIGEgYXByZXNlbnRhw6fDo28gZGVzdGEgbGljZW7Dp2EsIHZvY8OqIChvIGF1dG9yIChlcykgb3UgbyB0aXR1bGFyIGRvcyBkaXJlaXRvcyBkZSBhdXRvcikgY29uY2VkZSBhbyBSZXBvc2l0w7NyaW8gSW5zdGl0dWNpb25hbCBkYSBVRk1HIChSSS1VRk1HKSBvIGRpcmVpdG8gbsOjbyBleGNsdXNpdm8gZSBpcnJldm9nw6F2ZWwgZGUgcmVwcm9kdXppciBlL291IGRpc3RyaWJ1aXIgYSBzdWEgcHVibGljYcOnw6NvIChpbmNsdWluZG8gbyByZXN1bW8pIHBvciB0b2RvIG8gbXVuZG8gbm8gZm9ybWF0byBpbXByZXNzbyBlIGVsZXRyw7RuaWNvIGUgZW0gcXVhbHF1ZXIgbWVpbywgaW5jbHVpbmRvIG9zIGZvcm1hdG9zIMOhdWRpbyBvdSB2w61kZW8uCgpWb2PDqiBkZWNsYXJhIHF1ZSBjb25oZWNlIGEgcG9sw610aWNhIGRlIGNvcHlyaWdodCBkYSBlZGl0b3JhIGRvIHNldSBkb2N1bWVudG8gZSBxdWUgY29uaGVjZSBlIGFjZWl0YSBhcyBEaXJldHJpemVzIGRvIFJJLVVGTUcuCgpWb2PDqiBjb25jb3JkYSBxdWUgbyBSZXBvc2l0w7NyaW8gSW5zdGl0dWNpb25hbCBkYSBVRk1HIHBvZGUsIHNlbSBhbHRlcmFyIG8gY29udGXDumRvLCB0cmFuc3BvciBhIHN1YSBwdWJsaWNhw6fDo28gcGFyYSBxdWFscXVlciBtZWlvIG91IGZvcm1hdG8gcGFyYSBmaW5zIGRlIHByZXNlcnZhw6fDo28uCgpWb2PDqiB0YW1iw6ltIGNvbmNvcmRhIHF1ZSBvIFJlcG9zaXTDs3JpbyBJbnN0aXR1Y2lvbmFsIGRhIFVGTUcgcG9kZSBtYW50ZXIgbWFpcyBkZSB1bWEgY8OzcGlhIGRlIHN1YSBwdWJsaWNhw6fDo28gcGFyYSBmaW5zIGRlIHNlZ3VyYW7Dp2EsIGJhY2stdXAgZSBwcmVzZXJ2YcOnw6NvLgoKVm9jw6ogZGVjbGFyYSBxdWUgYSBzdWEgcHVibGljYcOnw6NvIMOpIG9yaWdpbmFsIGUgcXVlIHZvY8OqIHRlbSBvIHBvZGVyIGRlIGNvbmNlZGVyIG9zIGRpcmVpdG9zIGNvbnRpZG9zIG5lc3RhIGxpY2Vuw6dhLiBWb2PDqiB0YW1iw6ltIGRlY2xhcmEgcXVlIG8gZGVww7NzaXRvIGRlIHN1YSBwdWJsaWNhw6fDo28gbsOjbywgcXVlIHNlamEgZGUgc2V1IGNvbmhlY2ltZW50bywgaW5mcmluZ2UgZGlyZWl0b3MgYXV0b3JhaXMgZGUgbmluZ3XDqW0uCgpDYXNvIGEgc3VhIHB1YmxpY2HDp8OjbyBjb250ZW5oYSBtYXRlcmlhbCBxdWUgdm9jw6ogbsOjbyBwb3NzdWkgYSB0aXR1bGFyaWRhZGUgZG9zIGRpcmVpdG9zIGF1dG9yYWlzLCB2b2PDqiBkZWNsYXJhIHF1ZSBvYnRldmUgYSBwZXJtaXNzw6NvIGlycmVzdHJpdGEgZG8gZGV0ZW50b3IgZG9zIGRpcmVpdG9zIGF1dG9yYWlzIHBhcmEgY29uY2VkZXIgYW8gUmVwb3NpdMOzcmlvIEluc3RpdHVjaW9uYWwgZGEgVUZNRyBvcyBkaXJlaXRvcyBhcHJlc2VudGFkb3MgbmVzdGEgbGljZW7Dp2EsIGUgcXVlIGVzc2UgbWF0ZXJpYWwgZGUgcHJvcHJpZWRhZGUgZGUgdGVyY2Vpcm9zIGVzdMOhIGNsYXJhbWVudGUgaWRlbnRpZmljYWRvIGUgcmVjb25oZWNpZG8gbm8gdGV4dG8gb3Ugbm8gY29udGXDumRvIGRhIHB1YmxpY2HDp8OjbyBvcmEgZGVwb3NpdGFkYS4KCkNBU08gQSBQVUJMSUNBw4fDg08gT1JBIERFUE9TSVRBREEgVEVOSEEgU0lETyBSRVNVTFRBRE8gREUgVU0gUEFUUk9Dw41OSU8gT1UgQVBPSU8gREUgVU1BIEFHw4pOQ0lBIERFIEZPTUVOVE8gT1UgT1VUUk8gT1JHQU5JU01PLCBWT0PDiiBERUNMQVJBIFFVRSBSRVNQRUlUT1UgVE9ET1MgRSBRVUFJU1FVRVIgRElSRUlUT1MgREUgUkVWSVPDg08gQ09NTyBUQU1Cw4lNIEFTIERFTUFJUyBPQlJJR0HDh8OVRVMgRVhJR0lEQVMgUE9SIENPTlRSQVRPIE9VIEFDT1JETy4KCk8gUmVwb3NpdMOzcmlvIEluc3RpdHVjaW9uYWwgZGEgVUZNRyBzZSBjb21wcm9tZXRlIGEgaWRlbnRpZmljYXIgY2xhcmFtZW50ZSBvIHNldSBub21lKHMpIG91IG8ocykgbm9tZXMocykgZG8ocykgZGV0ZW50b3IoZXMpIGRvcyBkaXJlaXRvcyBhdXRvcmFpcyBkYSBwdWJsaWNhw6fDo28sIGUgbsOjbyBmYXLDoSBxdWFscXVlciBhbHRlcmHDp8OjbywgYWzDqW0gZGFxdWVsYXMgY29uY2VkaWRhcyBwb3IgZXN0YSBsaWNlbsOnYS4KRepositório de PublicaçõesPUBhttps://repositorio.ufmg.br/oaiopendoar:2022-04-29T19:26:40Repositório Institucional da UFMG - Universidade Federal de Minas Gerais (UFMG)false |
dc.title.pt_BR.fl_str_mv |
Analysis of the disposal of spent nuclear fuel in Brazil |
dc.title.alternative.pt_BR.fl_str_mv |
Análise da disposição do combustível nuclear irradiado no Brasil Análisis de la disposición de combustible nuclear gastado en Brasil Analyse du stockage du combustible nucléaire usé au Brésil |
title |
Analysis of the disposal of spent nuclear fuel in Brazil |
spellingShingle |
Analysis of the disposal of spent nuclear fuel in Brazil Raoni Adão Salviano Jonusan Spent fuel Deep geological repository Cost estimation Thermal analysis Site selection Engenharia nuclear Análise térmica Combustíveis nucleares Resíduos radioativos |
title_short |
Analysis of the disposal of spent nuclear fuel in Brazil |
title_full |
Analysis of the disposal of spent nuclear fuel in Brazil |
title_fullStr |
Analysis of the disposal of spent nuclear fuel in Brazil |
title_full_unstemmed |
Analysis of the disposal of spent nuclear fuel in Brazil |
title_sort |
Analysis of the disposal of spent nuclear fuel in Brazil |
author |
Raoni Adão Salviano Jonusan |
author_facet |
Raoni Adão Salviano Jonusan |
author_role |
author |
dc.contributor.advisor1.fl_str_mv |
Claubia Pereira Bezerra Lima |
dc.contributor.advisor1Lattes.fl_str_mv |
http://lattes.cnpq.br/1635197498453054 |
dc.contributor.advisor-co1.fl_str_mv |
Fernando Pereira de Faria |
dc.contributor.referee1.fl_str_mv |
Antonella Lombardi Costa |
dc.contributor.referee2.fl_str_mv |
Patrícia Amélia de Lima Reis |
dc.contributor.referee3.fl_str_mv |
Michel Melo Oliveira |
dc.contributor.referee4.fl_str_mv |
Flávia Schenato |
dc.contributor.referee5.fl_str_mv |
Francisco Javier Rios |
dc.contributor.authorLattes.fl_str_mv |
http://lattes.cnpq.br/2588322683897027 |
dc.contributor.author.fl_str_mv |
Raoni Adão Salviano Jonusan |
contributor_str_mv |
Claubia Pereira Bezerra Lima Fernando Pereira de Faria Antonella Lombardi Costa Patrícia Amélia de Lima Reis Michel Melo Oliveira Flávia Schenato Francisco Javier Rios |
dc.subject.por.fl_str_mv |
Spent fuel Deep geological repository Cost estimation Thermal analysis Site selection |
topic |
Spent fuel Deep geological repository Cost estimation Thermal analysis Site selection Engenharia nuclear Análise térmica Combustíveis nucleares Resíduos radioativos |
dc.subject.other.pt_BR.fl_str_mv |
Engenharia nuclear Análise térmica Combustíveis nucleares Resíduos radioativos |
description |
The disposal of radioactive waste has been the subject of scientific research since the beginning of the nuclear industry. For high-level waste or spent fuel, the final disposal in deep geological repositories is the global scientific consensus. In this doctoral thesis, aspects related to the process of disposal of spent nuclear fuel (SNF) in Brazil were studied, from a purely academic point of view. The radioactive decay process releases thermal energy that is absorbed by the geological environment. However, some of the safety barrier components have a maximum operating temperature limit. Furthermore, the heat released can help the migration of fluids in the geosphere. As the heat transfer process is passive, the repository must be dimensioned so that the thermal limits are not exceeded during its operation. The simulation of heat transfer allows the determination of the smallest acceptable geometric dimensions of the repository for each type of SNF. Given the Brazilian Government's apparent interest in reprocessed nuclear fuels, the thermal behavior of two reprocessed fuels for the Angra 2 nuclear power plant, a Mixed Oxide (MOX) and a thorium-enriched reprocessed fuel was simulated. The MOX fuel can be disposed of in a repository after 50 years of its removal from the reactor. The spent fuel containing thorium, however, cannot be disposed of in a repository under the same conditions, since the maximum safe temperature would be exceeded. The dimensioning of the repository for the SNF is an important piece of information for the process of selecting areas with the potential to house a geological repository. With the application of a method based on geographic information systems and multi-criteria analysis for the selection of an area for the construction of a repository for the SNF, sites of interest were selected for further. Candidate sites have areas greater than the minimum areas estimated as necessary by the heat transfer simulation. As both the nuclear fuel cycle and the total number of nuclear power plants to be built in this century remain undefined, there is no estimate of back-end costs in Brazil. To estimate the costs associated with this phase of the nuclear fuel life cycle, strategic scenarios were created. These scenarios, together with the possible fuel cycles, were modeled in the energy planning tool MESSAGE to estimate the amount of SNF generated. Using stochastic methods, the most likely total cost was calculated. Values range from $12.84 billion to $83.71 billion depending on the scenario. With this range, it was estimated that the energy sale value should be between 40% and 60% higher than the current value charged to finance the SNF disposal activities. |
publishDate |
2021 |
dc.date.issued.fl_str_mv |
2021-10-06 |
dc.date.accessioned.fl_str_mv |
2022-04-29T19:26:39Z |
dc.date.available.fl_str_mv |
2022-04-29T19:26:39Z |
dc.type.status.fl_str_mv |
info:eu-repo/semantics/publishedVersion |
dc.type.driver.fl_str_mv |
info:eu-repo/semantics/doctoralThesis |
format |
doctoralThesis |
status_str |
publishedVersion |
dc.identifier.uri.fl_str_mv |
http://hdl.handle.net/1843/41268 |
dc.identifier.orcid.pt_BR.fl_str_mv |
https://orcid.org/0000-0002-4533-2362 |
url |
http://hdl.handle.net/1843/41268 https://orcid.org/0000-0002-4533-2362 |
dc.language.iso.fl_str_mv |
eng |
language |
eng |
dc.rights.driver.fl_str_mv |
http://creativecommons.org/licenses/by-nc-nd/3.0/pt/ info:eu-repo/semantics/openAccess |
rights_invalid_str_mv |
http://creativecommons.org/licenses/by-nc-nd/3.0/pt/ |
eu_rights_str_mv |
openAccess |
dc.publisher.none.fl_str_mv |
Universidade Federal de Minas Gerais |
dc.publisher.program.fl_str_mv |
Programa de Pós-Graduação em Ciências e Técnicas Nucleares |
dc.publisher.initials.fl_str_mv |
UFMG |
dc.publisher.country.fl_str_mv |
Brasil |
dc.publisher.department.fl_str_mv |
ENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR |
publisher.none.fl_str_mv |
Universidade Federal de Minas Gerais |
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