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spelling paper:paper_09698043_v69_n12_p1924_Bortolussi2023-06-08T15:59:06Z Simulation of the neutron flux in the irradiation facility at RA-3 reactor Thorp, Silvia Ines González, Sara Josefina BNCT Irradiation facility simulation Neutron dosimetry Absorbed dose Argentina BNCT Computational model Experimental measurements Irradiation facilities Irradiation facility simulation Neutron dosimetry Thermal column Treatment plans Computer simulation Dosimetry Extraction Mica Neutron beams Neutron flux Plant shutdowns Neutron irradiation article controlled study mathematical analysis Monte Carlo method neutron capture therapy neutron dosimetry neutron radiation phantom priority journal radiation dose reactor simulation treatment planning A facility for the irradiation of a section of patients' explanted liver and lung was constructed at RA-3 reactor, Comisión Nacional de Energía Atómica, Argentina. The facility, located in the thermal column, is characterized by the possibility to insert and extract samples without the need to shutdown the reactor. In order to reach the best levels of security and efficacy of the treatment, it is necessary to perform an accurate dosimetry. The possibility to simulate neutron flux and absorbed dose in the explanted organs, together with the experimental dosimetry, allows setting more precise and effective treatment plans. To this end, a computational model of the entire reactor was set-up, and the simulations were validated with the experimental measurements performed in the facility. © 2011 Elsevier Ltd. Fil:Thorp, S.I. Universidad de Buenos Aires. Facultad de Ciencias Exactas y Naturales; Argentina. Fil:Gonzalez, S.J. Universidad de Buenos Aires. Facultad de Ciencias Exactas y Naturales; Argentina. 2011 https://bibliotecadigital.exactas.uba.ar/collection/paper/document/paper_09698043_v69_n12_p1924_Bortolussi http://hdl.handle.net/20.500.12110/paper_09698043_v69_n12_p1924_Bortolussi
institution Universidad de Buenos Aires
institution_str I-28
repository_str R-134
collection Biblioteca Digital - Facultad de Ciencias Exactas y Naturales (UBA)
topic BNCT
Irradiation facility simulation
Neutron dosimetry
Absorbed dose
Argentina
BNCT
Computational model
Experimental measurements
Irradiation facilities
Irradiation facility simulation
Neutron dosimetry
Thermal column
Treatment plans
Computer simulation
Dosimetry
Extraction
Mica
Neutron beams
Neutron flux
Plant shutdowns
Neutron irradiation
article
controlled study
mathematical analysis
Monte Carlo method
neutron capture therapy
neutron dosimetry
neutron radiation
phantom
priority journal
radiation dose
reactor
simulation
treatment planning
spellingShingle BNCT
Irradiation facility simulation
Neutron dosimetry
Absorbed dose
Argentina
BNCT
Computational model
Experimental measurements
Irradiation facilities
Irradiation facility simulation
Neutron dosimetry
Thermal column
Treatment plans
Computer simulation
Dosimetry
Extraction
Mica
Neutron beams
Neutron flux
Plant shutdowns
Neutron irradiation
article
controlled study
mathematical analysis
Monte Carlo method
neutron capture therapy
neutron dosimetry
neutron radiation
phantom
priority journal
radiation dose
reactor
simulation
treatment planning
Thorp, Silvia Ines
González, Sara Josefina
Simulation of the neutron flux in the irradiation facility at RA-3 reactor
topic_facet BNCT
Irradiation facility simulation
Neutron dosimetry
Absorbed dose
Argentina
BNCT
Computational model
Experimental measurements
Irradiation facilities
Irradiation facility simulation
Neutron dosimetry
Thermal column
Treatment plans
Computer simulation
Dosimetry
Extraction
Mica
Neutron beams
Neutron flux
Plant shutdowns
Neutron irradiation
article
controlled study
mathematical analysis
Monte Carlo method
neutron capture therapy
neutron dosimetry
neutron radiation
phantom
priority journal
radiation dose
reactor
simulation
treatment planning
description A facility for the irradiation of a section of patients' explanted liver and lung was constructed at RA-3 reactor, Comisión Nacional de Energía Atómica, Argentina. The facility, located in the thermal column, is characterized by the possibility to insert and extract samples without the need to shutdown the reactor. In order to reach the best levels of security and efficacy of the treatment, it is necessary to perform an accurate dosimetry. The possibility to simulate neutron flux and absorbed dose in the explanted organs, together with the experimental dosimetry, allows setting more precise and effective treatment plans. To this end, a computational model of the entire reactor was set-up, and the simulations were validated with the experimental measurements performed in the facility. © 2011 Elsevier Ltd.
author Thorp, Silvia Ines
González, Sara Josefina
author_facet Thorp, Silvia Ines
González, Sara Josefina
author_sort Thorp, Silvia Ines
title Simulation of the neutron flux in the irradiation facility at RA-3 reactor
title_short Simulation of the neutron flux in the irradiation facility at RA-3 reactor
title_full Simulation of the neutron flux in the irradiation facility at RA-3 reactor
title_fullStr Simulation of the neutron flux in the irradiation facility at RA-3 reactor
title_full_unstemmed Simulation of the neutron flux in the irradiation facility at RA-3 reactor
title_sort simulation of the neutron flux in the irradiation facility at ra-3 reactor
publishDate 2011
url https://bibliotecadigital.exactas.uba.ar/collection/paper/document/paper_09698043_v69_n12_p1924_Bortolussi
http://hdl.handle.net/20.500.12110/paper_09698043_v69_n12_p1924_Bortolussi
work_keys_str_mv AT thorpsilviaines simulationoftheneutronfluxintheirradiationfacilityatra3reactor
AT gonzalezsarajosefina simulationoftheneutronfluxintheirradiationfacilityatra3reactor
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