Commenced in January 2007
Frequency: Monthly
Edition: International
Paper Count: 31200
Study of the Late Phase of Core Degradation during Reflooding by Safety Injection System for VVER1000 with ASTECv2 Computer Code

Authors: Antoaneta Stefanova, Rositsa Gencheva, Pavlin Groudev


This paper presents the modeling approach in SBO sequence for VVER 1000 reactors and describes the reactor core behavior at late in-vessel phase in case of late reflooding by HPIS and gives preliminary results for the ASTECv2 validation. The work is focused on investigation of plant behavior during total loss of power and the operator actions. The main goal of these analyses is to assess the phenomena arising during the Station blackout (SBO) followed by primary side high pressure injection system (HPIS) reflooding of already damaged reactor core at very late “in-vessel” phase. The purpose of the analyses is to define how the later HPIS switching on can delay the time of vessel failure or possibly avoid vessel failure. The times for HPP injection were chosen based on previously performed investigations.

Keywords: VVER, operator action validation, ASTEC computer code, reflooding of overheated reactor core

Digital Object Identifier (DOI):

Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 1183


[1] Van Dorsselaere, J.P., Chatelard, P., Cranga, M., Guillard, G., et al., 2010. Validation status of the ASTEC integral code for severe accident simulation. Nuclear Technology 170, 397–415.
[2] Tusheva, P., Schäfer, F., Kliem, S., 2012. Investigations on optimization of accident management measures following a station blackout accident in a VVER-1000 pressurized water reactor, International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, Volume 1, Pages 11-24, Chicago, IL, Code 93719.
[3] Chatelard, P., Reinke, N., Arndt, S., Belon, S., Cantrel, L., Carenini, L., Chevalier-Jabet, K., Cousin, F., Eckel, J., Jacq, F., Marchetto, C., Mun, C., Piar, L., ASTEC V2 severe accident integral code main features, current V2.0 modeling status, perspectives, Nuclear Engineering and Design, Volume 272, June 2014, Pages 119-135, DOI: 10.1016/j.nucengdes.2013.06.040.
[4] J. Zou, D.Q. Guo, L.L. Tong, Evaluation of RCS injection strategy by normal residual heat removal system in severe accident management, Annals of Nuclear Energy, Volume 85, November 2015, Pages 166–174, doi:10.1016/j.anucene.2015.05.013.
[5] Hu, L., Zhang, Y., Li, L., Su, G.H., Tian, W., Qiu, S., Investigation of severe accident scenario of PWR response to LOCA along with SBO, Progress in Nuclear Energy, Volume 83, 1 August 2015, Pages 159-166, DOI: 10.1016/j.pnucene.2015.03.014.
[6] Tusheva, P., Schaefer, F., Reinke, N., Weiss, F.-P., Assessment of earlyphase accident management strategies in a station blackout scenario for VVER-1000 reactors, 18th International Conference on Nuclear Engineering, ICONE18, May 2010, Volume 4, Issue PARTS A AND B, 2010, Pages 921-932, DOI: 10.1115/ICONE18-29954.