Proceedings of the Workshop on in-vessel core debris retention and coolability

This conference on in-vessel core debris retention and coolability is composed of 37 papers grouped in three sessions: session 1 (Keynote papers: Key phenomena of late phase core melt progression, accident management strategies and status quo of severe fuel damage codes, In-vessel retention as a severe accident management scheme, GAREC analyses in support of in-vessel retention concept, Latest findings of RASPLAV project); session 2 - Experiments and model development with five sub-sessions: sub-session 1 (Debris bed heat transfer: Debris and Pool Formation/Heat Transfer in FARO-LWR: Experiments and Analyses, Evaporation and Flow of Coolant at the Bottom of a Particle-Bed modelling Relocated Debris, Investigations on the Coolability of Debris in the Lower Head with WABE-2D and MESOCO-2D, Uncertainty and Sensitivity Analysis of the Heat Transfer Mechanisms in the Lower Head, Simulation of the Arrival and Evolution of Debris in a PWR Lower Head with the SFD ICARE2 code), sub-session 2 (Corium properties, molten pool natural convection, and crust formation: Physico-chemistry and corium properties for in-vessel retention, Experimental data on heat flux distribution from volumetrically heated pool with frozen boundaries, Thermal hydraulic phenomena in corium pools - numerical simulation with TOLBIAC and experimental validation with BALI, TOLBIAC code simulations of some molten salt RASPLAV experiments, SIMECO experiments on in-vessel melt pool formation and heat transfer with and without a metallic layer, Numerical investigation of turbulent natural convection heat transfer in an internally-heated melt pool and metallic layer, Current status and validation of CON2D and 3D code, Free convection of heat-generating fluid in a constrained during experimental simulation of heat transfer in slice geometry), sub-session 3 (Gap formation and gap cooling: Quench of molten aluminum oxide associated with in-vessel debris retention by RPV internal water, Experimental investigations on in-vessel debris coolability through inherent cooling mechanisms, FOREVER experiments on thermal and mechanical behaviour of a reactor pressure vessel during a severe accident, Experimental studies of heat transfer in the slotted channels at the CTF facility, Experimental study on CHF in a hemispherical narrow gap, Experiments on heat removal in a gap between debris crust and RPV wall), sub-session 4 (Creep behaviour of reactor pressure vessel lower head: Experimental investigation of creep behaviour of RPV lower head, Lower head thermo-mechanical behaviour, Pressure vessel creep rupture analysis, Parametric studies on creep behavior of a reactor pressure vessel lower head, Study of RPV materials with respect to mechanical behaviour in case of complete core fusion), sub-session 5 (Ex-vessel boiling and critical heat flux phenomena: Natural convection boiling on the outer surface of a hemispherical vessel surrounded by a thermal insulation structure, Reactor vessel external cooling for corium retention SULTAN experimental program and modelling with CATHARE code), and session 3 (Scaling to reactor severe accident conditions and reactor applications: Potential for in-vessel retention through ex-vessel flooding, In-vessel core melt retention by RPV external cooling for high power PWR MAAP4 analysis on a LBLOCA scenario without SI, Coupled thermal-hydraulic analyses of the molten pool and pressure vessel during a severe accident, Studies on core melt behaviour in a BWR pressure vessel lower head, Analysis of reactor lower head penetration tube failure, Thermal hydraulic and mechanical aspects of in-vessel retention of core debris)