Adapting and applying SCDAP/RELAP5 to CANDU in-vessel retention studies

Author:

Mladin M.,Dupleac D.,Prisecaru I.,Mladin D.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference21 articles.

1. Summary of CANDU 6 probabilistic safety assessment study results;Allen;Nucl. Safety,1990

2. Blahnik, C., Luxat, J.C., Nijhawan, S., 1993. CANDU response to loss of all heat sinks. In: Proceedings of the Ninth ANS Meeting on Nuclear Thermalhydraulics, San Francisco.

3. Finite element analyses of a BWR vessel and penetration under severe accident conditions;Chavez;Nucl. Eng. Des.,1994

4. Boundary-layer-boiling and critical-heat-flux phenomena on a downward-facing hemispherical surface;Cheung;Nucl. Technol.,1999

5. Dupleac, D. et al., 2008. SCDAP/RELAP5 investigation on coolability of severely degraded CANDU 6 core – preliminary results. In: Proceedings of ICAPP’08, Anaheim, CA, USA.

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