Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants
Autor(a) principal: | |
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Data de Publicação: | 2013 |
Outros Autores: | , |
Tipo de documento: | Artigo de conferência |
Idioma: | eng |
Título da fonte: | Repositório Institucional do IEN |
Texto Completo: | http://carpedien.ien.gov.br:8080/handle/ien/2394 |
Resumo: | This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. It was postulated, then, the LOCA – Loss of coolant accident –, accident in the emergency cooling system of the nucleus ( without fusion), where was lost 66m³ of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis –Rj. The models mentioned above were applied in two scenarios ( plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1MBq/m³), during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x109 to 5x105 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (<11 kBq/m³). |
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Aguiar, André Silva deLapa, Celso Marcelo FranklinInstituto de Engenharia Nuclear2018-06-07T15:04:28Z2018-06-07T15:04:28Z2013-11http://carpedien.ien.gov.br:8080/handle/ien/2394Submitted by Marcele Costal de Castro (costalcastro@gmail.com) on 2018-06-07T15:04:28Z No. of bitstreams: 1 MODELING OF THE DISPERSION OF TRITIUM FROM POSTULATED ACCIDENTAL RELEASES FROM NUCLEAR POWER PLANTS.pdf: 885685 bytes, checksum: 7145aec56273244b81500d96b2e9707d (MD5)Made available in DSpace on 2018-06-07T15:04:28Z (GMT). No. of bitstreams: 1 MODELING OF THE DISPERSION OF TRITIUM FROM POSTULATED ACCIDENTAL RELEASES FROM NUCLEAR POWER PLANTS.pdf: 885685 bytes, checksum: 7145aec56273244b81500d96b2e9707d (MD5) Previous issue date: 2013-11This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. It was postulated, then, the LOCA – Loss of coolant accident –, accident in the emergency cooling system of the nucleus ( without fusion), where was lost 66m³ of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis –Rj. The models mentioned above were applied in two scenarios ( plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1MBq/m³), during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x109 to 5x105 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (<11 kBq/m³).engInstituto de Engenharia NuclearIENBrasilINAC 2013Nuclear power plantTritiumAccidental releasesModeling of the dispersion of tritium from postulated accidental releases from nuclear power plantsinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectVI INACinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IENinstname:Instituto de Engenharia Nuclearinstacron:IENLICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://carpedien.ien.gov.br:8080/xmlui/bitstream/ien/2394/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52ORIGINALMODELING OF THE DISPERSION OF TRITIUM FROM POSTULATED ACCIDENTAL RELEASES FROM NUCLEAR POWER PLANTS.pdfMODELING OF THE DISPERSION OF TRITIUM FROM POSTULATED ACCIDENTAL RELEASES FROM NUCLEAR POWER PLANTS.pdfapplication/pdf885685http://carpedien.ien.gov.br:8080/xmlui/bitstream/ien/2394/1/MODELING+OF+THE+DISPERSION+OF+TRITIUM+FROM+POSTULATED+ACCIDENTAL+RELEASES+FROM+NUCLEAR+POWER+PLANTS.pdf7145aec56273244b81500d96b2e9707dMD51ien/2394oai:carpedien.ien.gov.br:ien/23942018-06-07 12:04:28.143Dspace IENlsales@ien.gov.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 |
dc.title.pt_BR.fl_str_mv |
Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants |
title |
Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants |
spellingShingle |
Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants Aguiar, André Silva de INAC 2013 Nuclear power plant Tritium Accidental releases |
title_short |
Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants |
title_full |
Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants |
title_fullStr |
Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants |
title_full_unstemmed |
Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants |
title_sort |
Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants |
author |
Aguiar, André Silva de |
author_facet |
Aguiar, André Silva de Lapa, Celso Marcelo Franklin Instituto de Engenharia Nuclear |
author_role |
author |
author2 |
Lapa, Celso Marcelo Franklin Instituto de Engenharia Nuclear |
author2_role |
author author |
dc.contributor.author.fl_str_mv |
Aguiar, André Silva de Lapa, Celso Marcelo Franklin Instituto de Engenharia Nuclear |
dc.subject.por.fl_str_mv |
INAC 2013 Nuclear power plant Tritium Accidental releases |
topic |
INAC 2013 Nuclear power plant Tritium Accidental releases |
dc.description.abstract.por.fl_txt_mv |
This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. It was postulated, then, the LOCA – Loss of coolant accident –, accident in the emergency cooling system of the nucleus ( without fusion), where was lost 66m³ of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis –Rj. The models mentioned above were applied in two scenarios ( plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1MBq/m³), during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x109 to 5x105 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (<11 kBq/m³). |
description |
This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. It was postulated, then, the LOCA – Loss of coolant accident –, accident in the emergency cooling system of the nucleus ( without fusion), where was lost 66m³ of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis –Rj. The models mentioned above were applied in two scenarios ( plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1MBq/m³), during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x109 to 5x105 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (<11 kBq/m³). |
publishDate |
2013 |
dc.date.issued.fl_str_mv |
2013-11 |
dc.date.accessioned.fl_str_mv |
2018-06-07T15:04:28Z |
dc.date.available.fl_str_mv |
2018-06-07T15:04:28Z |
dc.type.status.fl_str_mv |
info:eu-repo/semantics/publishedVersion |
dc.type.driver.fl_str_mv |
info:eu-repo/semantics/conferenceObject |
status_str |
publishedVersion |
format |
conferenceObject |
dc.identifier.uri.fl_str_mv |
http://carpedien.ien.gov.br:8080/handle/ien/2394 |
url |
http://carpedien.ien.gov.br:8080/handle/ien/2394 |
dc.language.iso.fl_str_mv |
eng |
language |
eng |
dc.rights.driver.fl_str_mv |
info:eu-repo/semantics/openAccess |
eu_rights_str_mv |
openAccess |
dc.publisher.none.fl_str_mv |
Instituto de Engenharia Nuclear |
dc.publisher.initials.fl_str_mv |
IEN |
dc.publisher.country.fl_str_mv |
Brasil |
publisher.none.fl_str_mv |
Instituto de Engenharia Nuclear |
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