Physics of Coolability of Top Flooded Molten Corium
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
C8-1 Advanced Design Features for Severe Accident Mitigation including Combustion and Fires

Parimal Kulkarni (Bhabha Atomic Research Centre)
Raj Singh (Bhabha Atomic Research Centre)
Arun Kumar Nayak (Bhabha Atomic Research Centre)
Pallipattu Krishnan Vijayan (Bhabha Atomic Research Centre)
Dilip Saha (Bhabha Atomic Research Centre)
R. K. Sinha (Bhabha Atomic Research Centre)


In this paper, a mechanistic model has been presented for the corium coolability under top flooding conditions. The model has been validated with the experimental data of COMECO test facility available in literature. Simulations have been carried out using the model to explore the physics behind the corium coolability with MCCI under top flooding condition. Variations in the thermo-physical properties as a result of MCCI have been considered and its effect on coolability has been studied.

During a postulated severe accident in a nuclear reactor in case of ex-vessel scenario the molten corium can be relocated in the containment cavity forming a melt pool. In order to arrest further progression of severe accident, complete quenching of the molten corium pool is necessary. Most common way to deal with ex-vessel scenario is to flood the melt pool with large quantity of water. However, the mechanism of coolability is much more complex involving multi-component, multiphase heat, mass and momentum transfer.

Individual Conference-Paper Copies (Electronic Where Available):

  • For CNS members, the first 5 copies per calendar year are free, and additional copies are $10 each.
  • For non-members, the price is $25 for the first Conference-paper copy in a request, and $10 each for additional copies of papers in the same conference and in the same request.
  • Contact the CNS office to order reprints.