A preliminary study on concrete ablation during ex-vessel cooling in pre-flooded Westinghouse 3-loop NPP reactor cavity

Author:

Na Hanbee,Kang Dong Gu,Pak Sukyoung,Lee Hee Joon

Funder

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference40 articles.

1. Blose, R.E., Gronager, J.E., Suo-Anttila, A.J., Brockman, J.E., 1987. SWISS: Sustained Heated Metallic Melt/Concrete Interactions with Overlying Water Pools (No. NUREG/CR-4727).

2. Nuclear Heat Transport;El-Wakil,1979

3. Farmer, M.T., Lomperski, S., Kilsdonk, D.J., Aeschlimann, R.W., 2006. OECD / MCCI-2005-TR06 OECD MCCI Project Final Report.

4. Farmer, M.T., Spencer, B.W., Kilsdonk, D.J., Aeschlimann, R.W., 2000. Results of MACE core coolability experiments M0 and M1b, In: Proceeding of 8th International Conference on Nuclear Engineering (ICONE-8). Baltimore, MD.

5. Greene, G.A., Finrock, C., J. Klages, A., Schwarz, C.E., 1988. Experimental Studies on Melt Spreading, Bubbling Heat Transfer and Coolant Layer Boiling (No. NUREG/CP-0096). In: Proceedings of 16 th Water Reactor Safety Meeting.

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