Study of the Late Phase of Core Degradation during Reflooding by Safety Injection System for VVER1000 with ASTECv2 Computer Code
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.
[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.
[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.
@article{"International Journal of Engineering, Mathematical and Physical Sciences:70937", author = "Antoaneta Stefanova and Rositsa Gencheva and Pavlin Groudev", title = "Study of the Late Phase of Core Degradation during Reflooding by Safety Injection System for VVER1000 with ASTECv2 Computer Code", abstract = "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, reflooding of
overheated reactor core, ASTEC computer code.", volume = "9", number = "9", pages = "533-19", }