Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment

The article contains a numerical analysis of the secondary radiation contribution to the total radiation affecting the operational personnel during the dismantling activities of the contaminated equipment at a nuclear power plant. This study considers a widely applicable Monte Carlo particle tra...

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Main Authors: Stankunas Gediminas, Tonkunas Aurimas, Pabarcius Raimondas, Urbonas Rolandas
Format: Article
Language:English
Published: VINCA Institute of Nuclear Sciences 2013-01-01
Series:Nuclear Technology and Radiation Protection
Subjects:
Online Access:http://www.doiserbia.nb.rs/img/doi/1451-3994/2013/1451-39941303316S.pdf
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spelling doaj-0a39d78826f1424480ba68645ec5ef332020-11-24T23:13:26ZengVINCA Institute of Nuclear SciencesNuclear Technology and Radiation Protection1451-39942013-01-0128331632410.2298/NTRP1303316SEvaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipmentStankunas GediminasTonkunas AurimasPabarcius RaimondasUrbonas RolandasThe article contains a numerical analysis of the secondary radiation contribution to the total radiation affecting the operational personnel during the dismantling activities of the contaminated equipment at a nuclear power plant. This study considers a widely applicable Monte Carlo particle transport code MCNPX and real Ignalina nuclear power plant records. A simplified albedo method is investigated in order to analyze the selected geometrical design cases. Additionally, the impact of the secondary radiation on the personnel dose was analyzed. The numerical MCNPX simulation allowed ascertaining the optimal distance between the source and the wall for the working personnel in closed rooms with contaminated equipment. The developed dose rate maps of the secondary radiation showed cross-sectional distribution of the dose rate inside the enclosed area.http://www.doiserbia.nb.rs/img/doi/1451-3994/2013/1451-39941303316S.pdfradiationalbedodosedismantlingMonte Carlo method
collection DOAJ
language English
format Article
sources DOAJ
author Stankunas Gediminas
Tonkunas Aurimas
Pabarcius Raimondas
Urbonas Rolandas
spellingShingle Stankunas Gediminas
Tonkunas Aurimas
Pabarcius Raimondas
Urbonas Rolandas
Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment
Nuclear Technology and Radiation Protection
radiation
albedo
dose
dismantling
Monte Carlo method
author_facet Stankunas Gediminas
Tonkunas Aurimas
Pabarcius Raimondas
Urbonas Rolandas
author_sort Stankunas Gediminas
title Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment
title_short Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment
title_full Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment
title_fullStr Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment
title_full_unstemmed Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment
title_sort evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment
publisher VINCA Institute of Nuclear Sciences
series Nuclear Technology and Radiation Protection
issn 1451-3994
publishDate 2013-01-01
description The article contains a numerical analysis of the secondary radiation contribution to the total radiation affecting the operational personnel during the dismantling activities of the contaminated equipment at a nuclear power plant. This study considers a widely applicable Monte Carlo particle transport code MCNPX and real Ignalina nuclear power plant records. A simplified albedo method is investigated in order to analyze the selected geometrical design cases. Additionally, the impact of the secondary radiation on the personnel dose was analyzed. The numerical MCNPX simulation allowed ascertaining the optimal distance between the source and the wall for the working personnel in closed rooms with contaminated equipment. The developed dose rate maps of the secondary radiation showed cross-sectional distribution of the dose rate inside the enclosed area.
topic radiation
albedo
dose
dismantling
Monte Carlo method
url http://www.doiserbia.nb.rs/img/doi/1451-3994/2013/1451-39941303316S.pdf
work_keys_str_mv AT stankunasgediminas evaluationofthesecondaryradiationimpactonpersonnelduringthedismantlingofcontaminatednuclearequipment
AT tonkunasaurimas evaluationofthesecondaryradiationimpactonpersonnelduringthedismantlingofcontaminatednuclearequipment
AT pabarciusraimondas evaluationofthesecondaryradiationimpactonpersonnelduringthedismantlingofcontaminatednuclearequipment
AT urbonasrolandas evaluationofthesecondaryradiationimpactonpersonnelduringthedismantlingofcontaminatednuclearequipment
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