An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs

Author:

Park Jae Hong,Jeong Yong Hoon,Baek Won-Pil,Chang Soon Heung

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference19 articles.

1. Bernaz, L. et al., 1998. Thermal hydraulic phenomena in corium pools: numerical simulation with TOLBIAC and experimental validation with BALI. In: Proc. OECD/NEA/CSNI Workshop on In-Vessel Core Debris Retention and Coolability, 3–6 March Garching, Germany.

2. Cheung, F.B., Liu, Y.C., 1998. Critical Heat Flux (CHF) Phenomenon on a Downward Facing Curved Surface: Effects of Thermal Insulation (NUREG/CR-5534).

3. Cheung, F.B., Liu, Y.C., 1999. CHF Experiments to Support In-Vessel Retention Feasibility Study For an Evolutionary ALWR Design. Preliminary Final Project Report, EPRI WO# 5491-01.

4. Cheung, F.B., Haddad, K.H., Liu, Y.C., 1997. Critical Heat Flux (CHF) Phenomenon on a Downward Facing Curved Surface (NUREG/CR-6507).

5. Granovskiy, V.S. et al., 1995. An experimental study of the CHF at the external cooling of reactor vessel. In: Proc. Thermophysics-90 (in Russian).

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