Influence of crust formation on the heat load to a reactor vessel under an in-vessel retention condition

Author:

Park Joon-Soo,Park Hae-Kyun,Chung Bum-Jin

Funder

National Research Foundation of Korea

Korea Ministry of Science and ICT

Ministry of Science, ICT and Future Planning

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

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2. Comparison of 2-D and 3-D IVR experiments for oxide layer in the three-layer configuration;Bae;Nucl. Eng. Technol.,2020

3. Thermal hydraulic phenomena in corium pools: the BALI experiment;Bonnet,1999

4. Cho, Y.J., Park, H.S., Choi, M.H., Hwang, S.W., Noh, H.K., 2015, Development of assessment methodologies for corium coolability, Korea Institute of Nuclear Safety, KINS/HR-1410.

5. On heat transfer characteristics of real and simulant melt pool experiments;Dinh;Nucl. Eng. Des.,1997

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