Study of Influences of the Level of Zr Oxidation and Volumetric Heat Generation on Heat Transfer and Crust Formation Within CANDU Corium

Author:

Rezaee Mahsa1,David Dijo1,Lightstone Marilyn1,Tullis Stephen1

Affiliation:

1. McMaster University, 1280 Main Street W, Hamilton, Ontario L8S 4L8, Canada

Funder

CNL, UNENE, and the NSERC

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference19 articles.

1. R. MCLEAN “In-Vessel Retention (IVR) Design Features Phenomenology and Technical Basis in the CANDU Reactor ” Proc. Technical Mtg. on Phenomenology and Technologies Relevant to In-Vessel Melt Retention and Ex-Vessel Corium Cooling Shanghai China (2016).

2. S. K. GUPTA et al., “Analysis of Severe Accidents in Pressurized Heavy Water Reactors,” International Atomic Energy Agency (2008).

3. “Severe Accident Progression Without Operator Action ” Canadian Nuclear Safety Commission Staff (2015); http://nuclearsafety.gc.ca/.

4. P. M. MATHEW T. NITHEANANDAN and S. BUSHBY “Severe Core Damage Accident Progression Within a CANDU 6 Calandria Vessel ” Proc. 3rd European Review Mtg. on Severe Accident Research Nessebar Bulgaria (2008).

5. Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3.6 code

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