Neutron dose estimation in a zero power nuclear reactor

Autores
Triviño, Juan Sebastián; Vedelago, José Alberto; Cantargi, Florencia Olga; Keil, Walter Miguel; Figueroa, R.; Mattea, Facundo; Chautemps, Norma Adriana; Santibañez, M.; Valente, Mauro Andres
Año de publicación
2016
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
This work presents the characterization and contribution of neutron and gamma components to the absorbed dose in a zero power nuclear reactor. A dosimetric method based on Fricke gel was implemented to evaluate the separation between dose components in the mixed field. The validation of this proposed method was performed by means of direct measurements of neutron flux in different positions using Au and Mg-Ni activation foils. Monte Carlo simulations were conversely performed using the MCNP main code with a dedicated subroutine to incorporate the exact complete geometry of the nuclear reactor facility. Once nuclear fuel elements were defined, the simulations computed the different contributions to the absorbed dose in specific positions inside the core. Thermal/epithermal contributions of absorbed dose were assessed by means of Fricke gel dosimetry using different isotopic compositions aimed at modifying the sensitivity of the dosimeter for specific dose components. Clear distinctions between gamma and neutron capture dose were obtained. Both Monte Carlo simulations and experimental results provided reliable estimations about neutron flux rate as well as dose rate during the reactor operation. Simulations and experimental results are in good agreement in every positions measured and simulated in the core.
Fil: Triviño, Juan Sebastián. Universidad Nacional de Córdoba; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Vedelago, José Alberto. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Córdoba. Instituto de Física Enrique Gaviola. Universidad Nacional de Córdoba. Instituto de Física Enrique Gaviola; Argentina
Fil: Cantargi, Florencia Olga. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina
Fil: Keil, Walter Miguel. Universidad Nacional de Córdoba; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Figueroa, R.. Universidad de La Frontera; Chile
Fil: Mattea, Facundo. Universidad Nacional de Córdoba; Argentina. Universidad Nacional de Córdoba. Facultad de Ciencias Químicas; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Fil: Chautemps, Norma Adriana. Comisión Nacional de Energía Atómica; Argentina
Fil: Santibañez, M.. Universidad de La Frontera; Chile
Fil: Valente, Mauro Andres. Universidad de La Frontera; Chile. Universidad Nacional de Córdoba; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Córdoba. Instituto de Física Enrique Gaviola. Universidad Nacional de Córdoba. Instituto de Física Enrique Gaviola; Argentina
Materia
Fricke Gel Dosimetry
Mcnp
Monte Carlo Simulations
Thermal/Epithermal Neutron Flux
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:11336/58826
Acceder
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oai_identifier_str oai:ri.conicet.gov.ar:11336/58826
network_acronym_str CONICETDig
repository_id_str 3498
network_name_str CONICET Digital (CONICET)
spelling Neutron dose estimation in a zero power nuclear reactorTriviño, Juan SebastiánVedelago, José AlbertoCantargi, Florencia OlgaKeil, Walter MiguelFigueroa, R.Mattea, FacundoChautemps, Norma AdrianaSantibañez, M.Valente, Mauro AndresFricke Gel DosimetryMcnpMonte Carlo SimulationsThermal/Epithermal Neutron Fluxhttps://purl.org/becyt/ford/1.3https://purl.org/becyt/ford/1This work presents the characterization and contribution of neutron and gamma components to the absorbed dose in a zero power nuclear reactor. A dosimetric method based on Fricke gel was implemented to evaluate the separation between dose components in the mixed field. The validation of this proposed method was performed by means of direct measurements of neutron flux in different positions using Au and Mg-Ni activation foils. Monte Carlo simulations were conversely performed using the MCNP main code with a dedicated subroutine to incorporate the exact complete geometry of the nuclear reactor facility. Once nuclear fuel elements were defined, the simulations computed the different contributions to the absorbed dose in specific positions inside the core. Thermal/epithermal contributions of absorbed dose were assessed by means of Fricke gel dosimetry using different isotopic compositions aimed at modifying the sensitivity of the dosimeter for specific dose components. Clear distinctions between gamma and neutron capture dose were obtained. Both Monte Carlo simulations and experimental results provided reliable estimations about neutron flux rate as well as dose rate during the reactor operation. Simulations and experimental results are in good agreement in every positions measured and simulated in the core.Fil: Triviño, Juan Sebastián. Universidad Nacional de Córdoba; Argentina. Comisión Nacional de Energía Atómica; ArgentinaFil: Vedelago, José Alberto. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Córdoba. Instituto de Física Enrique Gaviola. Universidad Nacional de Córdoba. Instituto de Física Enrique Gaviola; ArgentinaFil: Cantargi, Florencia Olga. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; ArgentinaFil: Keil, Walter Miguel. Universidad Nacional de Córdoba; Argentina. Comisión Nacional de Energía Atómica; ArgentinaFil: Figueroa, R.. Universidad de La Frontera; ChileFil: Mattea, Facundo. Universidad Nacional de Córdoba; Argentina. Universidad Nacional de Córdoba. Facultad de Ciencias Químicas; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaFil: Chautemps, Norma Adriana. Comisión Nacional de Energía Atómica; ArgentinaFil: Santibañez, M.. Universidad de La Frontera; ChileFil: Valente, Mauro Andres. Universidad de La Frontera; Chile. Universidad Nacional de Córdoba; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Córdoba. Instituto de Física Enrique Gaviola. Universidad Nacional de Córdoba. Instituto de Física Enrique Gaviola; ArgentinaPergamon-Elsevier Science Ltd2016-10-17info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfapplication/pdfapplication/pdfapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/58826Triviño, Juan Sebastián; Vedelago, José Alberto; Cantargi, Florencia Olga; Keil, Walter Miguel; Figueroa, R.; et al.; Neutron dose estimation in a zero power nuclear reactor; Pergamon-Elsevier Science Ltd; Radiation Physics and Chemistry (Oxford); 127; 17-10-2016; 62-670969-806XCONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/http://www.sciencedirect.com/science/article/pii/S0969806X16301906info:eu-repo/semantics/altIdentifier/doi/10.1016/j.radphyschem.2016.06.011info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-09-29T09:34:03Zoai:ri.conicet.gov.ar:11336/58826instacron: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 09:34:03.608CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Neutron dose estimation in a zero power nuclear reactor
title Neutron dose estimation in a zero power nuclear reactor
spellingShingle Neutron dose estimation in a zero power nuclear reactor
Triviño, Juan Sebastián
Fricke Gel Dosimetry
Mcnp
Monte Carlo Simulations
Thermal/Epithermal Neutron Flux
title_short Neutron dose estimation in a zero power nuclear reactor
title_full Neutron dose estimation in a zero power nuclear reactor
title_fullStr Neutron dose estimation in a zero power nuclear reactor
title_full_unstemmed Neutron dose estimation in a zero power nuclear reactor
title_sort Neutron dose estimation in a zero power nuclear reactor
dc.creator.none.fl_str_mv Triviño, Juan Sebastián
Vedelago, José Alberto
Cantargi, Florencia Olga
Keil, Walter Miguel
Figueroa, R.
Mattea, Facundo
Chautemps, Norma Adriana
Santibañez, M.
Valente, Mauro Andres
author Triviño, Juan Sebastián
author_facet Triviño, Juan Sebastián
Vedelago, José Alberto
Cantargi, Florencia Olga
Keil, Walter Miguel
Figueroa, R.
Mattea, Facundo
Chautemps, Norma Adriana
Santibañez, M.
Valente, Mauro Andres
author_role author
author2 Vedelago, José Alberto
Cantargi, Florencia Olga
Keil, Walter Miguel
Figueroa, R.
Mattea, Facundo
Chautemps, Norma Adriana
Santibañez, M.
Valente, Mauro Andres
author2_role author
author
author
author
author
author
author
author
dc.subject.none.fl_str_mv Fricke Gel Dosimetry
Mcnp
Monte Carlo Simulations
Thermal/Epithermal Neutron Flux
topic Fricke Gel Dosimetry
Mcnp
Monte Carlo Simulations
Thermal/Epithermal Neutron Flux
purl_subject.fl_str_mv https://purl.org/becyt/ford/1.3
https://purl.org/becyt/ford/1
dc.description.none.fl_txt_mv This work presents the characterization and contribution of neutron and gamma components to the absorbed dose in a zero power nuclear reactor. A dosimetric method based on Fricke gel was implemented to evaluate the separation between dose components in the mixed field. The validation of this proposed method was performed by means of direct measurements of neutron flux in different positions using Au and Mg-Ni activation foils. Monte Carlo simulations were conversely performed using the MCNP main code with a dedicated subroutine to incorporate the exact complete geometry of the nuclear reactor facility. Once nuclear fuel elements were defined, the simulations computed the different contributions to the absorbed dose in specific positions inside the core. Thermal/epithermal contributions of absorbed dose were assessed by means of Fricke gel dosimetry using different isotopic compositions aimed at modifying the sensitivity of the dosimeter for specific dose components. Clear distinctions between gamma and neutron capture dose were obtained. Both Monte Carlo simulations and experimental results provided reliable estimations about neutron flux rate as well as dose rate during the reactor operation. Simulations and experimental results are in good agreement in every positions measured and simulated in the core.
Fil: Triviño, Juan Sebastián. Universidad Nacional de Córdoba; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Vedelago, José Alberto. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Córdoba. Instituto de Física Enrique Gaviola. Universidad Nacional de Córdoba. Instituto de Física Enrique Gaviola; Argentina
Fil: Cantargi, Florencia Olga. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina
Fil: Keil, Walter Miguel. Universidad Nacional de Córdoba; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Figueroa, R.. Universidad de La Frontera; Chile
Fil: Mattea, Facundo. Universidad Nacional de Córdoba; Argentina. Universidad Nacional de Córdoba. Facultad de Ciencias Químicas; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Fil: Chautemps, Norma Adriana. Comisión Nacional de Energía Atómica; Argentina
Fil: Santibañez, M.. Universidad de La Frontera; Chile
Fil: Valente, Mauro Andres. Universidad de La Frontera; Chile. Universidad Nacional de Córdoba; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Córdoba. Instituto de Física Enrique Gaviola. Universidad Nacional de Córdoba. Instituto de Física Enrique Gaviola; Argentina
description This work presents the characterization and contribution of neutron and gamma components to the absorbed dose in a zero power nuclear reactor. A dosimetric method based on Fricke gel was implemented to evaluate the separation between dose components in the mixed field. The validation of this proposed method was performed by means of direct measurements of neutron flux in different positions using Au and Mg-Ni activation foils. Monte Carlo simulations were conversely performed using the MCNP main code with a dedicated subroutine to incorporate the exact complete geometry of the nuclear reactor facility. Once nuclear fuel elements were defined, the simulations computed the different contributions to the absorbed dose in specific positions inside the core. Thermal/epithermal contributions of absorbed dose were assessed by means of Fricke gel dosimetry using different isotopic compositions aimed at modifying the sensitivity of the dosimeter for specific dose components. Clear distinctions between gamma and neutron capture dose were obtained. Both Monte Carlo simulations and experimental results provided reliable estimations about neutron flux rate as well as dose rate during the reactor operation. Simulations and experimental results are in good agreement in every positions measured and simulated in the core.
publishDate 2016
dc.date.none.fl_str_mv 2016-10-17
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/11336/58826
Triviño, Juan Sebastián; Vedelago, José Alberto; Cantargi, Florencia Olga; Keil, Walter Miguel; Figueroa, R.; et al.; Neutron dose estimation in a zero power nuclear reactor; Pergamon-Elsevier Science Ltd; Radiation Physics and Chemistry (Oxford); 127; 17-10-2016; 62-67
0969-806X
CONICET Digital
CONICET
url http://hdl.handle.net/11336/58826
identifier_str_mv Triviño, Juan Sebastián; Vedelago, José Alberto; Cantargi, Florencia Olga; Keil, Walter Miguel; Figueroa, R.; et al.; Neutron dose estimation in a zero power nuclear reactor; Pergamon-Elsevier Science Ltd; Radiation Physics and Chemistry (Oxford); 127; 17-10-2016; 62-67
0969-806X
CONICET Digital
CONICET
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/S0969806X16301906
info:eu-repo/semantics/altIdentifier/doi/10.1016/j.radphyschem.2016.06.011
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
application/pdf
application/pdf
application/pdf
application/pdf
dc.publisher.none.fl_str_mv Pergamon-Elsevier Science Ltd
publisher.none.fl_str_mv Pergamon-Elsevier Science Ltd
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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score 13.070432

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