In vessel corium propagation sensitivity study of reactor pressure vessel rupture time with PROCOR platform

Eleonora Skrzypek, Maciej Skrzypek, Laurent Saas, Romain LeTellier

Abstract


The problem of corium propagation for PWRs in the Reactor Pressure Vessel (RPV) and the timing of RPV failure is one of the
main issues of study in the area of severe accidents. The PROCOR numerical platform created by the CEA severe accident
laboratory is modelling corium propagation for LWRs, its relocation to the Lower Plenum and RPV failure. The idea behind the
platform was to provide a tool that is fast enough to be able to perform numerous calculations within a reasonable time frame in
order to deliver a statistical study. Work on the development of models that describe in-vessel issues is being pursued through
simplified phenomena modelling, their verification and sensitivity studies. Recent activities related to PROCOR development
involved cooperation between French CEA experts and Polish PhD students, who were engaged in the topics of core support
plate modelling and analysis of the phenomena occurring in a thin metallic layer on top of the corium pool. Those issues
were identified as strongly influencing the course of severe accidents and the timing of RPV failure. In some sensitivity
studies performed on a given generic high power Light Water Reactor with heavy reflector, two groups of RPV ruptures were
distinguished related to the two issues, which provided motivation for further work on these topics. The paper will present
a sensitivity study of corium propagation in order to identify the relevance of those two issues for the timing of RPV rupture.

Keywords


Sensitivity study, PROCOR Platform, IVMR strategy

Full Text:

PDF

References


F. Fichot, J.-M. Bonnet, B.Chaumont, Irsn views and perspectives on

in-vessel melt retention strategy for severe accident mitigation, in: EUROSAFE

Forum 2015, Brussels, Belgium, 2015.

B.R.Sehgal, Nuclear safety in light water reactors: Severe accident

phenomenology„ Elsevier, (2012) 550–551.

M. Sangiorgi, In-vessel melt retention (ivmr) analysis of a vver-1000

npp, in: 6th ASTEC user’s club/ 2nd CESAM workshop, 2015.

R.LeTellier, L.Saas, F.Payot (Eds.), Phenomenological analyses of

corium propagation in LWRs: the PROCOR software platform, Marseille,

France, 2015, eRMSAR 2015.

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.

R.LeTellier, L.Saas, S.Bajard, Transient stratification modelling of a

corium pool in a lwr vessel lower head, Nuclear Engineering and Design

(2015) 68–77.

F. Gaudier, Uranie : The cea/den uncertainty and sensitivity platform,

Procedia Social and Behavioral Sciences 2, Elsevier Ltd. (2010)

–7661.

D. Skrien, Object-Oriented Design Using Java (Jan. 2008).

ROOT Data Analysis Framework, User’s Guide (May 2014).

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.

P.Darnowski, E.Skrzypek, P. Mazgaj, K. Swirski, P. Gandrille, Total loss

of ac power analysis for epr reactor, Nuclear Engineering and Design

(2015) 8–18.

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.

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.

I.Lindholm, A review of dryout heat fluxes and coolabiliy of particle

beds, Tech. Rep. APRI 4, Stage 2 Report, VTT Energy, Finland (Apr.

.

H. Esmaili, M. Khatib-Rahbar, Analysis of in-vessel retention and exvessel

fuel coolant interaction for ap1000, Tech. Rep. NUREG/CR-

ERI/NRC04-201, U.S. Nuclear Regulatory Commission, Office

of Nuclear Regulatory Research (2004).

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.

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.

T. Chawla, S. Chan, Heat transfer from vertical/inclined boundaries

of heat-generating boiling pools, Journal of Heat Transfer 104 (1982)

–473.

J. Bonnet, J. Seiler, Thermohydraulic phenomena in corium pool: the

bali experiment, in: ICONE 7, Tokyo, Japan, 1999.


Refbacks

  • There are currently no refbacks.