| Project Number |
Project Acronym |
Project Title |
| 0064 |
ZirConCatcher |
Design of a nuclear reactor core melt catcher on the basis of zirconia concrete |
| 0833 |
METCOR |
Investigation of Corium Melt Interaction With NPP Reactor Vessel Steel |
| 0833.2 |
METCOR.2 |
Investigation of Corium Melt Interaction With NPP Reactor Vessel Steel |
| 1648.2 |
VVER-QUENCH |
Examination of VVER Fuel Behavior Under Severe Accident Conditions. Quench Stage |
| 1950.2 |
CORPHAD |
Phase Diagrams For Multicomponent Systems Containing Corium and Products of Its Interaction With NPP Materials |
| 2916 |
CHESS |
Development of the Models for Nuclear Fuel Behavior During Active Phase of the Chernobyl Accident |
| 2936 |
REACTOR CORE MELTING |
Modelling of Reactor Core Behaviour Under Severe Accident Conditions. Melt Formation, Relocation and Evolution of Molten Pool |
| 3194 |
PARAMETER |
Fuel Assembly Tests Under Severe Accident Conditions |
| 3345 |
EVAN |
Source Term Assessment at Ex-Vessel Stage of Severe Accident |
| 3592 |
METCOR-P |
Investigation of Corium Melt Interaction With NPP Reactor Vessel Steel |
| 3635 |
VVER-VESSEL |
Scale Experimental Investigation of the Thermal and Structural Integrity of the VVER Pressure Vessel Lower Head in Severe Accident |
| 3690 |
PARAMETER-2 |
Study of Fuel Assemblies under Severe Accident Top Quenching Conditions in the PARAMETER-SF Test Series |
| 3813 |
PRECOS |
Phase Relations in Corium Systems |
| 3831 |
LARGE SCALE MCCI |
Development and Experiments at Large-Scale Installation for Heating and Retention of Corium |
| 3876 |
THOMAS |
Thermo-Hydraulics of U-Zr-O Molten Pool under Oxidising Conditions in Multi-Scale Approach (Crucible - Bundle - Reactor Scales) |
| 4207 (STCU) |
CHERNOBYL SHELTER |
Long Time Behavior of Chernobyl Fuel |
| K-1265 |
INVECOR |
Experimental Study of the Processes at the Corium Melt Retention in the Reactor Pressure Vessel |
