Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System
Decommissioning of the Ignalina Nuclear Power Plant involves multiple problems. One of them is personnel radiation safety during the performance of dismantling activities. In this paper, modeling results of radiation doses during the dismantling of the pressurized tank from the emergency core coolin...
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| Format: | Article |
| Language: | English |
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Wiley
2013-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2013/576432 |
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| author | A. Simonis P. Poskas A. Sirvydas D. Grigaliuniene |
| author_facet | A. Simonis P. Poskas A. Sirvydas D. Grigaliuniene |
| author_sort | A. Simonis |
| collection | DOAJ |
| description | Decommissioning of the Ignalina Nuclear Power Plant involves multiple problems. One of them is personnel radiation safety during the performance of dismantling activities. In this paper, modeling results of radiation doses during the dismantling of the pressurized tank from the emergency core cooling system (ECCS PT) of RBMK-1500 reactor are presented. The radiological surveys indicate that the inner surface of the ECCS PT is contaminated with radioactive products of corrosion and sediments due to the radioactive water. The effective doses to the workers have been modeled for different strategies of ECCS PT dismantling. In order to select the optimal personnel radiation safety, the modeling has been performed by the means of computer code “VISIPLAN 3D ALARA Planning tool” developed by SCK CEN (Belgium). The impacts of dismantling tools, shielding types, and extract ventilation flow rate on effective doses during the dismantling of ECCS PT have been analyzed. The total effective personnel doses have been obtained by summarizing the effective personnel doses from various sources of exposure, that is, direct radiation from radioactive equipment, internal radiation due to inhalation of radioactive aerosols, and direct radiation from radioactive aerosols arising during hot cutting in premises. The uncertainty of the collective doses is also presented in this paper. |
| format | Article |
| id | doaj-art-88f06c2d1e184bc48bcd18349dd68f62 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2013-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-88f06c2d1e184bc48bcd18349dd68f622025-02-03T01:26:08ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832013-01-01201310.1155/2013/576432576432Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling SystemA. Simonis0P. Poskas1A. Sirvydas2D. Grigaliuniene3Nuclear Engineering Laboratory, Lithuanian Energy Institute, Breslaujos g. 3, 44403 Kaunas, LithuaniaNuclear Engineering Laboratory, Lithuanian Energy Institute, Breslaujos g. 3, 44403 Kaunas, LithuaniaNuclear Engineering Laboratory, Lithuanian Energy Institute, Breslaujos g. 3, 44403 Kaunas, LithuaniaNuclear Engineering Laboratory, Lithuanian Energy Institute, Breslaujos g. 3, 44403 Kaunas, LithuaniaDecommissioning of the Ignalina Nuclear Power Plant involves multiple problems. One of them is personnel radiation safety during the performance of dismantling activities. In this paper, modeling results of radiation doses during the dismantling of the pressurized tank from the emergency core cooling system (ECCS PT) of RBMK-1500 reactor are presented. The radiological surveys indicate that the inner surface of the ECCS PT is contaminated with radioactive products of corrosion and sediments due to the radioactive water. The effective doses to the workers have been modeled for different strategies of ECCS PT dismantling. In order to select the optimal personnel radiation safety, the modeling has been performed by the means of computer code “VISIPLAN 3D ALARA Planning tool” developed by SCK CEN (Belgium). The impacts of dismantling tools, shielding types, and extract ventilation flow rate on effective doses during the dismantling of ECCS PT have been analyzed. The total effective personnel doses have been obtained by summarizing the effective personnel doses from various sources of exposure, that is, direct radiation from radioactive equipment, internal radiation due to inhalation of radioactive aerosols, and direct radiation from radioactive aerosols arising during hot cutting in premises. The uncertainty of the collective doses is also presented in this paper.http://dx.doi.org/10.1155/2013/576432 |
| spellingShingle | A. Simonis P. Poskas A. Sirvydas D. Grigaliuniene Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System Science and Technology of Nuclear Installations |
| title | Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System |
| title_full | Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System |
| title_fullStr | Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System |
| title_full_unstemmed | Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System |
| title_short | Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System |
| title_sort | modeling of the radiation doses during dismantling of rbmk 1500 reactor pressurized tanks from emergency core cooling system |
| url | http://dx.doi.org/10.1155/2013/576432 |
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