Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I

Detalhes bibliográficos
Autor(a) principal: Lapa, Celso Marcelo Franklin
Data de Publicação: 2015
Outros Autores: Guamá, Daniel, Araújo, Jeferson, Instituto de Engenharia Nuclear
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/2352
Resumo: Probabilistic Risk Analysis (PRA) surges as a way to evaluate the risk of Nuclear Power Plants (NPPs) and to quantify it. Its objective was to track sequences of accidents and define mitigate actions to prevent core damage. But when the core is damaged the question is how to avoid releases of radionuclides to the environment. PRA evaluates this scenario too and is input to the Severe Accident Management Guidance (SAMG). This paper aims in the interaction between PRA and SAMG, both under development for the Brazilian NPPs, focusing in one specific Plant Damage State (PDS). The objective is to develop an Accident Progression Event Tree (APET) proposing the mitigate actions for the event, helping to understand the phenomena.
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spelling Lapa, Celso Marcelo FranklinGuamá, DanielAraújo, JefersonInstituto de Engenharia Nuclear2018-05-18T17:49:42Z2018-05-18T17:49:42Z2015-10http://carpedien.ien.gov.br:8080/handle/ien/2352Submitted by Marcele Costal de Castro (costalcastro@gmail.com) on 2018-05-18T17:49:42Z No. of bitstreams: 1 INSIGHTS OF PROBABILISTIC RISK ANALYSIS ON THE DEVELOPMENT OF SEVERE ACCIDENT MANAGEMENT GUIDANCE A CASE STUDY FOR A PLANT SIMILAR TO ANGRA I.pdf: 259044 bytes, checksum: e74cc3ac4c6dc75047e36346fc0907e7 (MD5)Made available in DSpace on 2018-05-18T17:49:42Z (GMT). No. of bitstreams: 1 INSIGHTS OF PROBABILISTIC RISK ANALYSIS ON THE DEVELOPMENT OF SEVERE ACCIDENT MANAGEMENT GUIDANCE A CASE STUDY FOR A PLANT SIMILAR TO ANGRA I.pdf: 259044 bytes, checksum: e74cc3ac4c6dc75047e36346fc0907e7 (MD5) Previous issue date: 2015-10Probabilistic Risk Analysis (PRA) surges as a way to evaluate the risk of Nuclear Power Plants (NPPs) and to quantify it. Its objective was to track sequences of accidents and define mitigate actions to prevent core damage. But when the core is damaged the question is how to avoid releases of radionuclides to the environment. PRA evaluates this scenario too and is input to the Severe Accident Management Guidance (SAMG). This paper aims in the interaction between PRA and SAMG, both under development for the Brazilian NPPs, focusing in one specific Plant Damage State (PDS). The objective is to develop an Accident Progression Event Tree (APET) proposing the mitigate actions for the event, helping to understand the phenomena.engInstituto de Engenharia NuclearIENBrasilINAC 2015Reactor safety analysisAngra IProbabilistic risk analysisInsights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra Iinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectXIX ENFIRinfo: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/2352/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52ORIGINALINSIGHTS OF PROBABILISTIC RISK ANALYSIS ON THE DEVELOPMENT OF SEVERE ACCIDENT MANAGEMENT GUIDANCE A CASE STUDY FOR A PLANT SIMILAR TO ANGRA I.pdfINSIGHTS OF PROBABILISTIC RISK ANALYSIS ON THE DEVELOPMENT OF SEVERE ACCIDENT MANAGEMENT GUIDANCE A CASE STUDY FOR A PLANT SIMILAR TO ANGRA I.pdfapplication/pdf259044http://carpedien.ien.gov.br:8080/xmlui/bitstream/ien/2352/1/INSIGHTS+OF+PROBABILISTIC+RISK+ANALYSIS+ON+THE+DEVELOPMENT+OF+SEVERE+ACCIDENT+MANAGEMENT+GUIDANCE+A+CASE+STUDY+FOR+A+PLANT+SIMILAR+TO+ANGRA+I.pdfe74cc3ac4c6dc75047e36346fc0907e7MD51ien/2352oai:carpedien.ien.gov.br:ien/23522018-05-18 14:49:42.846Dspace IENlsales@ien.gov.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
dc.title.pt_BR.fl_str_mv Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I
title Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I
spellingShingle Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I
Lapa, Celso Marcelo Franklin
INAC 2015
Reactor safety analysis
Angra I
Probabilistic risk analysis
title_short Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I
title_full Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I
title_fullStr Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I
title_full_unstemmed Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I
title_sort Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to Angra I
author Lapa, Celso Marcelo Franklin
author_facet Lapa, Celso Marcelo Franklin
Guamá, Daniel
Araújo, Jeferson
Instituto de Engenharia Nuclear
author_role author
author2 Guamá, Daniel
Araújo, Jeferson
Instituto de Engenharia Nuclear
author2_role author
author
author
dc.contributor.author.fl_str_mv Lapa, Celso Marcelo Franklin
Guamá, Daniel
Araújo, Jeferson
Instituto de Engenharia Nuclear
dc.subject.por.fl_str_mv INAC 2015
Reactor safety analysis
Angra I
Probabilistic risk analysis
topic INAC 2015
Reactor safety analysis
Angra I
Probabilistic risk analysis
dc.description.abstract.por.fl_txt_mv Probabilistic Risk Analysis (PRA) surges as a way to evaluate the risk of Nuclear Power Plants (NPPs) and to quantify it. Its objective was to track sequences of accidents and define mitigate actions to prevent core damage. But when the core is damaged the question is how to avoid releases of radionuclides to the environment. PRA evaluates this scenario too and is input to the Severe Accident Management Guidance (SAMG). This paper aims in the interaction between PRA and SAMG, both under development for the Brazilian NPPs, focusing in one specific Plant Damage State (PDS). The objective is to develop an Accident Progression Event Tree (APET) proposing the mitigate actions for the event, helping to understand the phenomena.
description Probabilistic Risk Analysis (PRA) surges as a way to evaluate the risk of Nuclear Power Plants (NPPs) and to quantify it. Its objective was to track sequences of accidents and define mitigate actions to prevent core damage. But when the core is damaged the question is how to avoid releases of radionuclides to the environment. PRA evaluates this scenario too and is input to the Severe Accident Management Guidance (SAMG). This paper aims in the interaction between PRA and SAMG, both under development for the Brazilian NPPs, focusing in one specific Plant Damage State (PDS). The objective is to develop an Accident Progression Event Tree (APET) proposing the mitigate actions for the event, helping to understand the phenomena.
publishDate 2015
dc.date.issued.fl_str_mv 2015-10
dc.date.accessioned.fl_str_mv 2018-05-18T17:49:42Z
dc.date.available.fl_str_mv 2018-05-18T17:49:42Z
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/2352
url http://carpedien.ien.gov.br:8080/handle/ien/2352
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
dc.source.none.fl_str_mv reponame:Repositório Institucional do IEN
instname:Instituto de Engenharia Nuclear
instacron:IEN
reponame_str Repositório Institucional do IEN
collection Repositório Institucional do IEN
instname_str Instituto de Engenharia Nuclear
instacron_str IEN
institution IEN
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