Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants

The decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (...

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Main Authors: Egidijus Babilas, Eugenijus Ušpuras, Sigitas Rimkevičius, Gintautas Dundulis, Mindaugas Vaišnoras
Format: Article
Language:English
Published: Wiley 2015-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2015/650810
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author Egidijus Babilas
Eugenijus Ušpuras
Sigitas Rimkevičius
Gintautas Dundulis
Mindaugas Vaišnoras
author_facet Egidijus Babilas
Eugenijus Ušpuras
Sigitas Rimkevičius
Gintautas Dundulis
Mindaugas Vaišnoras
author_sort Egidijus Babilas
collection DOAJ
description The decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (International Atomic Energy Agency, 2006). This paper presents safety assessment approach used in Lithuania during the development of the first dismantling and decontamination project for Ignalina NPP. The paper will mainly focus on the identification and assessment of the hazards raised due to dismantling and decontamination activities at Ignalina Nuclear Power Plant and on the assessment of the nonradiological and radiological consequences of the indicated most dangerous initiating event. The drop of heavy item was indicated as one of most dangerous initiating events for the discussed Ignalina Nuclear Power Plant dismantling and decontamination project. For the analysis of the nonradiological impact the finite element model for the load drop force calculation was developed. The radiological impact was evaluated in those accident cases which would lead to the worst radiological consequences. The assessments results show that structural integrity of the building and supporting columns of building structures will be maintained and radiological consequences are lower than the annual regulatory operator dose limit.
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institution Kabale University
issn 1687-6075
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language English
publishDate 2015-01-01
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series Science and Technology of Nuclear Installations
spelling doaj-art-92a502baf9214fdcb399c7331399e2692025-02-03T06:07:56ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832015-01-01201510.1155/2015/650810650810Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power PlantsEgidijus Babilas0Eugenijus Ušpuras1Sigitas Rimkevičius2Gintautas Dundulis3Mindaugas Vaišnoras4Lithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas, LithuaniaLithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas, LithuaniaLithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas, LithuaniaLithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas, LithuaniaLithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas, LithuaniaThe decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (International Atomic Energy Agency, 2006). This paper presents safety assessment approach used in Lithuania during the development of the first dismantling and decontamination project for Ignalina NPP. The paper will mainly focus on the identification and assessment of the hazards raised due to dismantling and decontamination activities at Ignalina Nuclear Power Plant and on the assessment of the nonradiological and radiological consequences of the indicated most dangerous initiating event. The drop of heavy item was indicated as one of most dangerous initiating events for the discussed Ignalina Nuclear Power Plant dismantling and decontamination project. For the analysis of the nonradiological impact the finite element model for the load drop force calculation was developed. The radiological impact was evaluated in those accident cases which would lead to the worst radiological consequences. The assessments results show that structural integrity of the building and supporting columns of building structures will be maintained and radiological consequences are lower than the annual regulatory operator dose limit.http://dx.doi.org/10.1155/2015/650810
spellingShingle Egidijus Babilas
Eugenijus Ušpuras
Sigitas Rimkevičius
Gintautas Dundulis
Mindaugas Vaišnoras
Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants
Science and Technology of Nuclear Installations
title Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants
title_full Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants
title_fullStr Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants
title_full_unstemmed Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants
title_short Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants
title_sort safety assessment of low contaminated equipment dismantling at nuclear power plants
url http://dx.doi.org/10.1155/2015/650810
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AT gintautasdundulis safetyassessmentoflowcontaminatedequipmentdismantlingatnuclearpowerplants
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