Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel

Autores
Kempf, Rodolfo; Troiani, Horacio Esteban; Fortis, Ana María
Año de publicación
2013
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
This paper presents a project to study the effect of lead factors on the mechanical behaviour of the SA-508 type 3 Reactor Pressure Vessel (RPV) steel used in the reactor under construction Atucha II in Argentina. Charpy-V notch specimens of this steel were irradiated at the RA1 experimental reactor at a temperature of 275 C with two lead factors (186 and 93). The neutron flux was 3.71 1015 n m2 s1 and 1.85 1015 n m2 s1 (E > 1 MeV) respectively. In both cases, the fluence was 6.6 1021 n m2 , which is equivalent to that received by the PHWR Atucha II RPV in 10 years of full power irradiation. The results of Charpy tests revealed significant embrittlement both in the DT = 14 C and DT = 21 C shifts of the ductile–brittle transition temperatures (DBTT) and in the reduction of the maximum energy absorbed. This result shows that the shift of the DBTT with a lead factor of 93 is larger than that obtained with a lead factor of 186. Then, the results of irradiation in experimental reactors (MTR) with high lead factors may not be conservative with respect to the actual RPV embrittlement.
Fil: Kempf, Rodolfo. Comision Nacional de Energia Atomica. Gerencia Quimica. CAC; Argentina
Fil: Troiani, Horacio Esteban. Comision Nacional de Energia Atomica. Gerencia del Area de Investigaciones y Aplicaciones no Nucleares. Gerencia de Fisica (CAB); Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Area de Energía Nuclear. Instituto Balseiro; Argentina
Fil: Fortis, Ana María. Universidad Nacional de San Martín; Argentina. Comision Nacional de Energia Atomica. Gerencia Quimica. CAC; Argentina
Materia
Steel
Pressure Vessel
Atucha Ii
Nivel de accesibilidad
acceso abierto
Condiciones de uso
https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
Repositorio
CONICET Digital (CONICET)
Institución
Consejo Nacional de Investigaciones Científicas y Técnicas
OAI Identificador
oai:ri.conicet.gov.ar:11336/9842

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network_name_str CONICET Digital (CONICET)
spelling Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steelKempf, RodolfoTroiani, Horacio EstebanFortis, Ana MaríaSteelPressure VesselAtucha Iihttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2https://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2This paper presents a project to study the effect of lead factors on the mechanical behaviour of the SA-508 type 3 Reactor Pressure Vessel (RPV) steel used in the reactor under construction Atucha II in Argentina. Charpy-V notch specimens of this steel were irradiated at the RA1 experimental reactor at a temperature of 275 C with two lead factors (186 and 93). The neutron flux was 3.71 1015 n m2 s1 and 1.85 1015 n m2 s1 (E > 1 MeV) respectively. In both cases, the fluence was 6.6 1021 n m2 , which is equivalent to that received by the PHWR Atucha II RPV in 10 years of full power irradiation. The results of Charpy tests revealed significant embrittlement both in the DT = 14 C and DT = 21 C shifts of the ductile–brittle transition temperatures (DBTT) and in the reduction of the maximum energy absorbed. This result shows that the shift of the DBTT with a lead factor of 93 is larger than that obtained with a lead factor of 186. Then, the results of irradiation in experimental reactors (MTR) with high lead factors may not be conservative with respect to the actual RPV embrittlement.Fil: Kempf, Rodolfo. Comision Nacional de Energia Atomica. Gerencia Quimica. CAC; ArgentinaFil: Troiani, Horacio Esteban. Comision Nacional de Energia Atomica. Gerencia del Area de Investigaciones y Aplicaciones no Nucleares. Gerencia de Fisica (CAB); Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Area de Energía Nuclear. Instituto Balseiro; ArgentinaFil: Fortis, Ana María. Universidad Nacional de San Martín; Argentina. Comision Nacional de Energia Atomica. Gerencia Quimica. CAC; ArgentinaElsevier Science2013-03info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/9842Kempf, Rodolfo; Troiani, Horacio Esteban; Fortis, Ana María; Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel; Elsevier Science; Journal of Nuclear Materials; 434; 1-3; 3-2013; 411-4160022-3115enginfo:eu-repo/semantics/altIdentifier/url/http://www.sciencedirect.com/science/article/pii/S0022311512006617info:eu-repo/semantics/altIdentifier/doi/10.1016/j.jnucmat.2012.12.004info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-09-29T10:09:09Zoai:ri.conicet.gov.ar:11336/9842instacron:CONICETInstitucionalhttp://ri.conicet.gov.ar/Organismo científico-tecnológicoNo correspondehttp://ri.conicet.gov.ar/oai/requestdasensio@conicet.gov.ar; lcarlino@conicet.gov.arArgentinaNo correspondeNo correspondeNo correspondeopendoar:34982025-09-29 10:09:09.367CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel
title Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel
spellingShingle Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel
Kempf, Rodolfo
Steel
Pressure Vessel
Atucha Ii
title_short Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel
title_full Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel
title_fullStr Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel
title_full_unstemmed Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel
title_sort Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel
dc.creator.none.fl_str_mv Kempf, Rodolfo
Troiani, Horacio Esteban
Fortis, Ana María
author Kempf, Rodolfo
author_facet Kempf, Rodolfo
Troiani, Horacio Esteban
Fortis, Ana María
author_role author
author2 Troiani, Horacio Esteban
Fortis, Ana María
author2_role author
author
dc.subject.none.fl_str_mv Steel
Pressure Vessel
Atucha Ii
topic Steel
Pressure Vessel
Atucha Ii
purl_subject.fl_str_mv https://purl.org/becyt/ford/2.5
https://purl.org/becyt/ford/2
https://purl.org/becyt/ford/2.5
https://purl.org/becyt/ford/2
dc.description.none.fl_txt_mv This paper presents a project to study the effect of lead factors on the mechanical behaviour of the SA-508 type 3 Reactor Pressure Vessel (RPV) steel used in the reactor under construction Atucha II in Argentina. Charpy-V notch specimens of this steel were irradiated at the RA1 experimental reactor at a temperature of 275 C with two lead factors (186 and 93). The neutron flux was 3.71 1015 n m2 s1 and 1.85 1015 n m2 s1 (E > 1 MeV) respectively. In both cases, the fluence was 6.6 1021 n m2 , which is equivalent to that received by the PHWR Atucha II RPV in 10 years of full power irradiation. The results of Charpy tests revealed significant embrittlement both in the DT = 14 C and DT = 21 C shifts of the ductile–brittle transition temperatures (DBTT) and in the reduction of the maximum energy absorbed. This result shows that the shift of the DBTT with a lead factor of 93 is larger than that obtained with a lead factor of 186. Then, the results of irradiation in experimental reactors (MTR) with high lead factors may not be conservative with respect to the actual RPV embrittlement.
Fil: Kempf, Rodolfo. Comision Nacional de Energia Atomica. Gerencia Quimica. CAC; Argentina
Fil: Troiani, Horacio Esteban. Comision Nacional de Energia Atomica. Gerencia del Area de Investigaciones y Aplicaciones no Nucleares. Gerencia de Fisica (CAB); Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Area de Energía Nuclear. Instituto Balseiro; Argentina
Fil: Fortis, Ana María. Universidad Nacional de San Martín; Argentina. Comision Nacional de Energia Atomica. Gerencia Quimica. CAC; Argentina
description This paper presents a project to study the effect of lead factors on the mechanical behaviour of the SA-508 type 3 Reactor Pressure Vessel (RPV) steel used in the reactor under construction Atucha II in Argentina. Charpy-V notch specimens of this steel were irradiated at the RA1 experimental reactor at a temperature of 275 C with two lead factors (186 and 93). The neutron flux was 3.71 1015 n m2 s1 and 1.85 1015 n m2 s1 (E > 1 MeV) respectively. In both cases, the fluence was 6.6 1021 n m2 , which is equivalent to that received by the PHWR Atucha II RPV in 10 years of full power irradiation. The results of Charpy tests revealed significant embrittlement both in the DT = 14 C and DT = 21 C shifts of the ductile–brittle transition temperatures (DBTT) and in the reduction of the maximum energy absorbed. This result shows that the shift of the DBTT with a lead factor of 93 is larger than that obtained with a lead factor of 186. Then, the results of irradiation in experimental reactors (MTR) with high lead factors may not be conservative with respect to the actual RPV embrittlement.
publishDate 2013
dc.date.none.fl_str_mv 2013-03
dc.type.none.fl_str_mv info:eu-repo/semantics/article
info:eu-repo/semantics/publishedVersion
http://purl.org/coar/resource_type/c_6501
info:ar-repo/semantics/articulo
format article
status_str publishedVersion
dc.identifier.none.fl_str_mv http://hdl.handle.net/11336/9842
Kempf, Rodolfo; Troiani, Horacio Esteban; Fortis, Ana María; Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel; Elsevier Science; Journal of Nuclear Materials; 434; 1-3; 3-2013; 411-416
0022-3115
url http://hdl.handle.net/11336/9842
identifier_str_mv Kempf, Rodolfo; Troiani, Horacio Esteban; Fortis, Ana María; Effect of lead factors on the embrittlement of RPV SA-508 cl 3 steel; Elsevier Science; Journal of Nuclear Materials; 434; 1-3; 3-2013; 411-416
0022-3115
dc.language.none.fl_str_mv eng
language eng
dc.relation.none.fl_str_mv info:eu-repo/semantics/altIdentifier/url/http://www.sciencedirect.com/science/article/pii/S0022311512006617
info:eu-repo/semantics/altIdentifier/doi/10.1016/j.jnucmat.2012.12.004
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
eu_rights_str_mv openAccess
rights_invalid_str_mv https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv Elsevier Science
publisher.none.fl_str_mv Elsevier Science
dc.source.none.fl_str_mv reponame:CONICET Digital (CONICET)
instname:Consejo Nacional de Investigaciones Científicas y Técnicas
reponame_str CONICET Digital (CONICET)
collection CONICET Digital (CONICET)
instname_str Consejo Nacional de Investigaciones Científicas y Técnicas
repository.name.fl_str_mv CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicas
repository.mail.fl_str_mv dasensio@conicet.gov.ar; lcarlino@conicet.gov.ar
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