Prevention and Investigations of Core Degradation in Case of Beyond Design Accidents of the 2400 MWTH Gas-Cooled Fast Reactor
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
G4-2 - Gas Cooled Fast Reactors and Very High Temperature Reactors; System Calculations

Frederic Bertrand (CEA/DEN Cadarache)
Vincent Gatin (CEA/DEN Cadarache)
Fabrice Bentivoglio (CEA/DEN Grenoble)
Christine Gueneau (CEA/DEN Saclay)


The present paper deals with studies carried out to assess the ability of the core of the Gas Fast

Reactor (GFR) to withstand beyond design accidents. The work presented here is aimed at

simulating the behaviour of this core by using analytical models whose input parameters are

calculated with the CATHARE2 code. Among possible severe accident initiators, the

Unprotected Loss Of Coolant Accident (ULOCA of 3 Inches diameter) is investigated in detail

in the paper with CATHARE2. Additionally, a simplified pessimistic assessment of the effect of

a postulated power excursion that could result from the failure of prevention provisions is


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