Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia

Autores
Bortolussi, S.; Protti, N.; Ferrari, M.; Postuma, I.; Fatemi, S.; Prata, M.; Ballarini, F.; Carante, M.P.; Farias, R.; González, Sara Josefina; Marrale, M.; Gallo, S.; Bartolotta, A.; Iacoviello, G.; Nigg, D.; Altieri, S.
Año de publicación
2018
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is (1.20±0.03)×1010 cm−2 s−1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2×10-13 Gy/(n/cm2).
Fil: Bortolussi, S.. Universita Degli Studi Di Pavia; Italia
Fil: Protti, N.. Universita Degli Studi Di Pavia; Italia
Fil: Ferrari, M.. Universita Degli Studi Di Pavia; Italia
Fil: Postuma, I.. Universita Degli Studi Di Pavia; Italia
Fil: Fatemi, S.. Universita Degli Studi Di Pavia; Italia
Fil: Prata, M.. Universita Degli Studi Di Pavia; Italia
Fil: Ballarini, F.. Universita Degli Studi Di Pavia; Italia
Fil: Carante, M.P.. Universita Degli Studi Di Pavia; Italia
Fil: Farias, R.. Comisión Nacional de Energía Atómica; Argentina
Fil: González, Sara Josefina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Marrale, M.. Universita Degli Studi Di Pavia; Italia
Fil: Gallo, S.. Università degli Studi di Milano; Italia
Fil: Bartolotta, A.. Universita Degli Studi Di Palermo.; Italia
Fil: Iacoviello, G.. No especifíca;
Fil: Nigg, D.. Idaho National Laboratory; Estados Unidos
Fil: Altieri, S.. Universita Degli Studi Di Pavia; Italia
Materia
ALANINE DOSIMETRY
BNCT
NEUTRON ACTIVATION
NEUTRON FLUX MEASUREMENTS
PHOTON DOSIMETRY
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:11336/134536
Acceder
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oai_identifier_str oai:ri.conicet.gov.ar:11336/134536
network_acronym_str CONICETDig
repository_id_str 3498
network_name_str CONICET Digital (CONICET)
spelling Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of PaviaBortolussi, S.Protti, N.Ferrari, M.Postuma, I.Fatemi, S.Prata, M.Ballarini, F.Carante, M.P.Farias, R.González, Sara JosefinaMarrale, M.Gallo, S.Bartolotta, A.Iacoviello, G.Nigg, D.Altieri, S.ALANINE DOSIMETRYBNCTNEUTRON ACTIVATIONNEUTRON FLUX MEASUREMENTSPHOTON DOSIMETRYhttps://purl.org/becyt/ford/1.3https://purl.org/becyt/ford/1University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is (1.20±0.03)×1010 cm−2 s−1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2×10-13 Gy/(n/cm2).Fil: Bortolussi, S.. Universita Degli Studi Di Pavia; ItaliaFil: Protti, N.. Universita Degli Studi Di Pavia; ItaliaFil: Ferrari, M.. Universita Degli Studi Di Pavia; ItaliaFil: Postuma, I.. Universita Degli Studi Di Pavia; ItaliaFil: Fatemi, S.. Universita Degli Studi Di Pavia; ItaliaFil: Prata, M.. Universita Degli Studi Di Pavia; ItaliaFil: Ballarini, F.. Universita Degli Studi Di Pavia; ItaliaFil: Carante, M.P.. Universita Degli Studi Di Pavia; ItaliaFil: Farias, R.. Comisión Nacional de Energía Atómica; ArgentinaFil: González, Sara Josefina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica; ArgentinaFil: Marrale, M.. Universita Degli Studi Di Pavia; ItaliaFil: Gallo, S.. Università degli Studi di Milano; ItaliaFil: Bartolotta, A.. Universita Degli Studi Di Palermo.; ItaliaFil: Iacoviello, G.. No especifíca;Fil: Nigg, D.. Idaho National Laboratory; Estados UnidosFil: Altieri, S.. Universita Degli Studi Di Pavia; ItaliaElsevier2018-01info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/134536Bortolussi, S.; Protti, N.; Ferrari, M.; Postuma, I.; Fatemi, S.; et al.; Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia; Elsevier; Beam Interactions with Materials and Atoms; 414; 1-2018; 113-1200168-583XCONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/https://linkinghub.elsevier.com/retrieve/pii/S0168583X17309424info:eu-repo/semantics/altIdentifier/doi/10.1016/j.nimb.2017.10.023info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-09-03T09:53:17Zoai:ri.conicet.gov.ar:11336/134536instacron: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:34982025-09-03 09:53:17.735CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia
title Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia
spellingShingle Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia
Bortolussi, S.
ALANINE DOSIMETRY
BNCT
NEUTRON ACTIVATION
NEUTRON FLUX MEASUREMENTS
PHOTON DOSIMETRY
title_short Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia
title_full Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia
title_fullStr Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia
title_full_unstemmed Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia
title_sort Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia
dc.creator.none.fl_str_mv Bortolussi, S.
Protti, N.
Ferrari, M.
Postuma, I.
Fatemi, S.
Prata, M.
Ballarini, F.
Carante, M.P.
Farias, R.
González, Sara Josefina
Marrale, M.
Gallo, S.
Bartolotta, A.
Iacoviello, G.
Nigg, D.
Altieri, S.
author Bortolussi, S.
author_facet Bortolussi, S.
Protti, N.
Ferrari, M.
Postuma, I.
Fatemi, S.
Prata, M.
Ballarini, F.
Carante, M.P.
Farias, R.
González, Sara Josefina
Marrale, M.
Gallo, S.
Bartolotta, A.
Iacoviello, G.
Nigg, D.
Altieri, S.
author_role author
author2 Protti, N.
Ferrari, M.
Postuma, I.
Fatemi, S.
Prata, M.
Ballarini, F.
Carante, M.P.
Farias, R.
González, Sara Josefina
Marrale, M.
Gallo, S.
Bartolotta, A.
Iacoviello, G.
Nigg, D.
Altieri, S.
author2_role author
author
author
author
author
author
author
author
author
author
author
author
author
author
author
dc.subject.none.fl_str_mv ALANINE DOSIMETRY
BNCT
NEUTRON ACTIVATION
NEUTRON FLUX MEASUREMENTS
PHOTON DOSIMETRY
topic ALANINE DOSIMETRY
BNCT
NEUTRON ACTIVATION
NEUTRON FLUX MEASUREMENTS
PHOTON DOSIMETRY
purl_subject.fl_str_mv https://purl.org/becyt/ford/1.3
https://purl.org/becyt/ford/1
dc.description.none.fl_txt_mv University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is (1.20±0.03)×1010 cm−2 s−1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2×10-13 Gy/(n/cm2).
Fil: Bortolussi, S.. Universita Degli Studi Di Pavia; Italia
Fil: Protti, N.. Universita Degli Studi Di Pavia; Italia
Fil: Ferrari, M.. Universita Degli Studi Di Pavia; Italia
Fil: Postuma, I.. Universita Degli Studi Di Pavia; Italia
Fil: Fatemi, S.. Universita Degli Studi Di Pavia; Italia
Fil: Prata, M.. Universita Degli Studi Di Pavia; Italia
Fil: Ballarini, F.. Universita Degli Studi Di Pavia; Italia
Fil: Carante, M.P.. Universita Degli Studi Di Pavia; Italia
Fil: Farias, R.. Comisión Nacional de Energía Atómica; Argentina
Fil: González, Sara Josefina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Marrale, M.. Universita Degli Studi Di Pavia; Italia
Fil: Gallo, S.. Università degli Studi di Milano; Italia
Fil: Bartolotta, A.. Universita Degli Studi Di Palermo.; Italia
Fil: Iacoviello, G.. No especifíca;
Fil: Nigg, D.. Idaho National Laboratory; Estados Unidos
Fil: Altieri, S.. Universita Degli Studi Di Pavia; Italia
description University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is (1.20±0.03)×1010 cm−2 s−1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2×10-13 Gy/(n/cm2).
publishDate 2018
dc.date.none.fl_str_mv 2018-01
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/11336/134536
Bortolussi, S.; Protti, N.; Ferrari, M.; Postuma, I.; Fatemi, S.; et al.; Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia; Elsevier; Beam Interactions with Materials and Atoms; 414; 1-2018; 113-120
0168-583X
CONICET Digital
CONICET
url http://hdl.handle.net/11336/134536
identifier_str_mv Bortolussi, S.; Protti, N.; Ferrari, M.; Postuma, I.; Fatemi, S.; et al.; Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia; Elsevier; Beam Interactions with Materials and Atoms; 414; 1-2018; 113-120
0168-583X
CONICET Digital
CONICET
dc.language.none.fl_str_mv eng
language eng
dc.relation.none.fl_str_mv info:eu-repo/semantics/altIdentifier/url/https://linkinghub.elsevier.com/retrieve/pii/S0168583X17309424
info:eu-repo/semantics/altIdentifier/doi/10.1016/j.nimb.2017.10.023
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
publisher.none.fl_str_mv Elsevier
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 13.13397

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