In vessel corium propagation sensitivity study of reactor pressure vessel rupture time with PROCOR platform
Abstract
The problem of corium propagation for PWRs in the Reactor Pressure Vessel (RPV) and the timing of RPV failure is one of themain issues of study in the area of severe accidents. The PROCOR numerical platform created by the CEA severe accidentlaboratory is modelling corium propagation for LWRs, its relocation to the Lower Plenum and RPV failure. The idea behind theplatform was to provide a tool that is fast enough to be able to perform numerous calculations within a reasonable time frame inorder to deliver a statistical study. Work on the development of models that describe in-vessel issues is being pursued throughsimplified phenomena modelling, their verification and sensitivity studies. Recent activities related to PROCOR developmentinvolved cooperation between French CEA experts and Polish PhD students, who were engaged in the topics of core supportplate modelling and analysis of the phenomena occurring in a thin metallic layer on top of the corium pool. Those issueswere identified as strongly influencing the course of severe accidents and the timing of RPV failure. In some sensitivitystudies performed on a given generic high power Light Water Reactor with heavy reflector, two groups of RPV ruptures weredistinguished related to the two issues, which provided motivation for further work on these topics. The paper will presenta sensitivity study of corium propagation in order to identify the relevance of those two issues for the timing of RPV rupture.References
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Forum 2015, Brussels, Belgium, 2015.
[2] B.R.Sehgal, Nuclear safety in light water reactors: Severe accident
phenomenology„ Elsevier, (2012) 550–551.
[3] M. Sangiorgi, In-vessel melt retention (ivmr) analysis of a vver-1000
npp, in: 6th ASTEC user’s club/ 2nd CESAM workshop, 2015.
[4] R.LeTellier, L.Saas, F.Payot (Eds.), Phenomenological analyses of
corium propagation in LWRs: the PROCOR software platform, Marseille,
France, 2015, eRMSAR 2015.
[5] L. Saas, R. L. Tellier, S. Bajard, A simplified geometrical model for
transient corium propagation in core for an lwr with heavy reflector, in:
International Congress on Advances in Nuclear Power Plants, 2015.
[6] R.LeTellier, L.Saas, S.Bajard, Transient stratification modelling of a
corium pool in a lwr vessel lower head, Nuclear Engineering and Design
287 (2015) 68–77.
[7] F. Gaudier, Uranie : The cea/den uncertainty and sensitivity platform,
Procedia Social and Behavioral Sciences 2, Elsevier Ltd. (2010)
7660–7661.
[8] D. Skrien, Object-Oriented Design Using Java (Jan. 2008).
[9] ROOT Data Analysis Framework, User’s Guide (May 2014).
[10] H. Loeffler, J. Peschke, M. Sonnenkalb, Classical event tree analysis
and dynamic event tree analysis for high pressure core melt accidents
in a german pwr, in: OECD International Workshop on Level 2 PSA
and Severe Accident Management, Koeln, Germany, 2004.
[11] P.Darnowski, E.Skrzypek, P. Mazgaj, K. Swirski, P. Gandrille, Total loss
of ac power analysis for epr reactor, Nuclear Engineering and Design
289 (2015) 8–18.
[12] A. Bonelli, O. Mazzantini, M. Sonnenkalb, Station black-out analysis
with melcor 1.8.6 code for atucha 2 nuclear power plant, Science and
Technology of Nuclear Installations 2012.
[13] J. S. et al., Equations for solidification of corium without sparging gas
- scaling criteria, in: OECD workshop on ex-vessel debris coolability,
Karlsruhe, Germany, 1999.
[14] I.Lindholm, A review of dryout heat fluxes and coolabiliy of particle
beds, Tech. Rep. APRI 4, Stage 2 Report, VTT Energy, Finland (Apr.
2002).
[15] H. Esmaili, M. Khatib-Rahbar, Analysis of in-vessel retention and exvessel
fuel coolant interaction for ap1000, Tech. Rep. NUREG/CR-
6849 ERI/NRC04-201, U.S. Nuclear Regulatory Commission, Office
of Nuclear Regulatory Research (2004).
[16] S. Globe, D. Dropkin, Natural convection heat transfer in liquids confined
by two horizontal plates and heated from below, Journal of Heat
Transfer 81 (1959) 24–28.
[17] S. Churchill, H. Chu, Correlating equations of laminar rand turbulent
free convection from a vertical plate, International Journal of Heat and
Mass Transfer 18 (1975) 1323–1329.
[18] T. Chawla, S. Chan, Heat transfer from vertical/inclined boundaries
of heat-generating boiling pools, Journal of Heat Transfer 104 (1982)
465–473.
[19] J. Bonnet, J. Seiler, Thermohydraulic phenomena in corium pool: the
bali experiment, in: ICONE 7, Tokyo, Japan, 1999.
Published
2017-07-21
How to Cite
SKRZYPEK, Eleonora et al.
In vessel corium propagation sensitivity study of reactor pressure vessel rupture time with PROCOR platform.
Journal of Power Technologies, [S.l.], v. 97, n. 2, p. 110--116, july 2017.
ISSN 2083-4195.
Available at: <https://papers.itc.pw.edu.pl/index.php/JPT/article/view/844>. Date accessed: 21 dec. 2024.
Issue
Section
Nuclear Power
Keywords
Sensitivity study, PROCOR Platform, IVMR strategy
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