CATHARE Assessment of PACTEL LOCA Experiments with Accident Management

This paper summarizes the analysis results of three PACTEL experiments, carried out with the advanced thermal-hydraulic system computer CATHARE 2 code as a part of the second work package WP2 (analytical work) of the EC project “Improved Accident Management of VVER nuclear power plants” (IMPAM-VVER)...

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Main Authors: Luben Sabotinov, Heikki Purhonen, Vesa Riikonen
Format: Article
Language:English
Published: Hindawi Limited 2010-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2010/783204
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author Luben Sabotinov
Heikki Purhonen
Vesa Riikonen
author_facet Luben Sabotinov
Heikki Purhonen
Vesa Riikonen
author_sort Luben Sabotinov
collection DOAJ
description This paper summarizes the analysis results of three PACTEL experiments, carried out with the advanced thermal-hydraulic system computer CATHARE 2 code as a part of the second work package WP2 (analytical work) of the EC project “Improved Accident Management of VVER nuclear power plants” (IMPAM-VVER). The three LOCA experiments, conducted on the Finnish test facility PACTEL (VVER-440 model), represent 7.4% cold leg breaks with combination of secondary bleed and primary bleed and feed and different actuation modes of the passive safety injection. The code was used for both defining and analyzing the experiments, and to assess its capabilities in predicting the associated complex VVER-related phenomena. The code results are in reasonable agreement with the measurements, and the important physical phenomena are well predicted, although still further improvement and validation might be necessary.
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spelling doaj.art-0aebfec15aa6478f841943cb90087ce92022-12-22T03:57:52ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832010-01-01201010.1155/2010/783204783204CATHARE Assessment of PACTEL LOCA Experiments with Accident ManagementLuben Sabotinov0Heikki Purhonen1Vesa Riikonen2IRSN, B. P.17 - 92262 Fontenay-aux-Roses, FranceLTKK, P.O. Box 20, 53851 Lappeenranta, FinlandLTKK, P.O. Box 20, 53851 Lappeenranta, FinlandThis paper summarizes the analysis results of three PACTEL experiments, carried out with the advanced thermal-hydraulic system computer CATHARE 2 code as a part of the second work package WP2 (analytical work) of the EC project “Improved Accident Management of VVER nuclear power plants” (IMPAM-VVER). The three LOCA experiments, conducted on the Finnish test facility PACTEL (VVER-440 model), represent 7.4% cold leg breaks with combination of secondary bleed and primary bleed and feed and different actuation modes of the passive safety injection. The code was used for both defining and analyzing the experiments, and to assess its capabilities in predicting the associated complex VVER-related phenomena. The code results are in reasonable agreement with the measurements, and the important physical phenomena are well predicted, although still further improvement and validation might be necessary.http://dx.doi.org/10.1155/2010/783204
spellingShingle Luben Sabotinov
Heikki Purhonen
Vesa Riikonen
CATHARE Assessment of PACTEL LOCA Experiments with Accident Management
Science and Technology of Nuclear Installations
title CATHARE Assessment of PACTEL LOCA Experiments with Accident Management
title_full CATHARE Assessment of PACTEL LOCA Experiments with Accident Management
title_fullStr CATHARE Assessment of PACTEL LOCA Experiments with Accident Management
title_full_unstemmed CATHARE Assessment of PACTEL LOCA Experiments with Accident Management
title_short CATHARE Assessment of PACTEL LOCA Experiments with Accident Management
title_sort cathare assessment of pactel loca experiments with accident management
url http://dx.doi.org/10.1155/2010/783204
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