Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

Abstract External or internal hazards, combined with multiple failures of components and safety systems or human errors can lead to a reactor core melt. In that case the reactor pressure vessel is the last barrier to keep the molten materials inside the reactor and to prevent further challenges to the nuclear power plant structures and consequently to the environment. In-vessel melt retention by external vessel cooling is a possible mitigative severe accident measure. Up to the moment it is not considered as a severe accident management strategy for VVER-1000 reactors. In this paper we analyse the possibility of in-vessel melt retention for a generic pressurized water VVER-1000 reactor during the late in-vessel phase of a postulated station blackout scenario. We developed a numerical model describing the thermal behaviour of a segregated molten pool situated in the lower plenum of the reactor pressure vessel and the thermo-mechanic behaviour of the vessel wall. The finite element code ANSYS® was used for the simulations. The results show that the highest thermo-mechanical loads are observed in the vertical part of the vessel wall, which is in contact with the molten metal. Parameter studies on the thickness of the metal layer have also been performed. Without flooding, the vessel wall will fail, as the necessary temperature for a balanced heat release from the external surface via radiation is near to or above the melting point of the steel. However, the external flooding could help the retention of the corium within the reactor pressure vessel.

[1]  Fan-bill B. Cheung,et al.  In-Vessel Retention of Molten Corium: Lessons Learned and Outstanding Issues , 2008 .

[2]  S. Nukiyama The Maximum and Minimum Values of the Heat Q Transmitted from Metal to Boiling Water under Atmospheric Pressure , 1966 .

[3]  T. G. Theofanous,et al.  Assessment of reactor vessel integrity (ARVI) , 2003 .

[4]  Alex Galperin,et al.  Implementation of multi-group cross-section methodology in BGCore MC-depletion code , 2008 .

[5]  Marc Barrachin,et al.  Corium phase equilibria based on MASCA, METCOR and CORPHAD results , 2008 .

[6]  T. C. Chawla,et al.  Heat Transfer From Vertical/Inclined Boundaries of Heat-Generating Boiling Pools , 1982 .

[8]  A. Miassoedov,et al.  In-vessel melt pool coolibility test—Description and results of LIVE experiments , 2010 .

[9]  O. Kymäläinen,et al.  In-vessel retention of corium at the Loviisa plant , 1997 .

[10]  G. L. Thinnes,et al.  Potential for AP600 in-vessel retention through ex-vessel flooding , 1997 .

[11]  Hans-Georg Willschütz Thermomechanische Modellierung eines Reaktordruckbehälters in der Spätphase eines Kernschmelzunfalls , 2005 .

[13]  B. R. Sehgal,et al.  Heat Transfer Processes in Reactor Vessel Lower Plenum During Late Phase of In-Vessel Core Melt Progression , 2002 .

[15]  O. Kymäläinen,et al.  Heat flux distribution from a volumetrically heated pool with high Rayleigh number , 1994 .

[16]  Sevostian Bechta,et al.  Water boiling on the corium melt surface under VVER severe accident conditions , 2000 .

[17]  F. Jacq,et al.  The ASTEC Integral Code for Severe Accident Simulation , 2009 .

[18]  Hae Min Park,et al.  The effect of the geometric scale on the critical heat flux for the top of the reactor vessel lower head , 2012 .

[19]  Florian Fichot,et al.  Progress on PWR Lower Head Failure Predictive Models , 2008 .

[20]  Sandro Paci,et al.  Thematic network for a Phebus FPT1 international standard problem (THENPHEBISP) , 2005 .

[21]  B. R. Sehgal,et al.  Recursively coupled thermal and mechanical FEM-analysis of lower plenum creep failure experiments , 2006 .

[22]  D. Dropkin,et al.  Natural-Convection Heat Transfer in Liquids Confined by Two Horizontal Plates and Heated From Below , 1959 .

[23]  T. G. Theofanous,et al.  The first results from the ACOPO experiment , 1997 .

[24]  V. G. Asmolov,et al.  Challenges left in the area of in-vessel melt retention , 2001 .

[25]  Eberhard Altstadt,et al.  Coupled thermal structural analysis of LWR vessel creep failure experiments , 2001 .

[26]  B. R. Sehgal,et al.  Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure , 2003 .

[27]  O. Kymäläinen,et al.  In-vessel coolability and retention of a core melt , 1997 .

[28]  S. Churchill,et al.  Correlating equations for laminar and turbulent free convection from a vertical plate , 1975 .