Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings

Data analyses of radioactive contamination of the RBMK-1500 reactor’s steam pipelines (SP) and components of high pressure rings (HPR) are presented in this paper. Also, modelled results of the SP-HPR system are compared to the results of other RBMK-1500 systems at Ignalina NPP Unit 1. Characteristi...

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Main Authors: G. Poškas, P. Poškas, A. Šimonis
Format: Article
Language:English
Published: Hindawi Limited 2019-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2019/8736173
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spelling doaj-dadd2cb97ecf4ecaadf1f8878646f7602020-11-25T02:26:14ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832019-01-01201910.1155/2019/87361738736173Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure RingsG. Poškas0P. Poškas1A. Šimonis2Lithuanian Energy Institute, Nuclear Engineering Laboratory, Breslaujos G. 3, Kaunas LT-44403, LithuaniaLithuanian Energy Institute, Nuclear Engineering Laboratory, Breslaujos G. 3, Kaunas LT-44403, LithuaniaLithuanian Energy Institute, Nuclear Engineering Laboratory, Breslaujos G. 3, Kaunas LT-44403, LithuaniaData analyses of radioactive contamination of the RBMK-1500 reactor’s steam pipelines (SP) and components of high pressure rings (HPR) are presented in this paper. Also, modelled results of the SP-HPR system are compared to the results of other RBMK-1500 systems at Ignalina NPP Unit 1. Characteristics of SP-HPR components, thermal-hydraulic conditions of the coolant, and system operational regimes were evaluated employing the computer code LLWAA-DECOM (Tractebel Energy Engineering, Belgium). The presented results complement radiological characterization activities and facilitate the decommissioning process of nuclear facilities with RBMK type reactors. Analysis of the modelled results showed that the spread of radioactive contamination is very uneven between different components of the SP-HPR. The overall activity level of deposits of the SP-HPR is mostly determined by activated corrosion products and is lower than the activity level in the main circulation circuit (MCC) and nonpurified water subsystem activity of the purification and cooling system (PCS).http://dx.doi.org/10.1155/2019/8736173
collection DOAJ
language English
format Article
sources DOAJ
author G. Poškas
P. Poškas
A. Šimonis
spellingShingle G. Poškas
P. Poškas
A. Šimonis
Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings
Science and Technology of Nuclear Installations
author_facet G. Poškas
P. Poškas
A. Šimonis
author_sort G. Poškas
title Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings
title_short Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings
title_full Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings
title_fullStr Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings
title_full_unstemmed Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings
title_sort assessment of the radioactive contamination of the rbmk-1500 reactor’s steam pipelines and high pressure rings
publisher Hindawi Limited
series Science and Technology of Nuclear Installations
issn 1687-6075
1687-6083
publishDate 2019-01-01
description Data analyses of radioactive contamination of the RBMK-1500 reactor’s steam pipelines (SP) and components of high pressure rings (HPR) are presented in this paper. Also, modelled results of the SP-HPR system are compared to the results of other RBMK-1500 systems at Ignalina NPP Unit 1. Characteristics of SP-HPR components, thermal-hydraulic conditions of the coolant, and system operational regimes were evaluated employing the computer code LLWAA-DECOM (Tractebel Energy Engineering, Belgium). The presented results complement radiological characterization activities and facilitate the decommissioning process of nuclear facilities with RBMK type reactors. Analysis of the modelled results showed that the spread of radioactive contamination is very uneven between different components of the SP-HPR. The overall activity level of deposits of the SP-HPR is mostly determined by activated corrosion products and is lower than the activity level in the main circulation circuit (MCC) and nonpurified water subsystem activity of the purification and cooling system (PCS).
url http://dx.doi.org/10.1155/2019/8736173
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