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Science and Technology of Nuclear Installations
Volume 2010, Article ID 783204, 8 pages
Research Article

CATHARE Assessment of PACTEL LOCA Experiments with Accident Management

1IRSN, B. P.17 - 92262 Fontenay-aux-Roses, France
2LTKK, P.O. Box 20, 53851 Lappeenranta, Finland

Received 19 May 2009; Revised 27 January 2010; Accepted 1 February 2010

Academic Editor: Dubravko Pevec

Copyright © 2010 Luben Sabotinov et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


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.