Simulation of the in-vessel retention device heat-removal capability of AP-1000 during a core meltdown accident-Reference-Cited by-同舟云学术

Simulation of the in-vessel retention device heat-removal capability of AP-1000 during a core meltdown accident

Published:2017-01 Issue: Volume:99 Page:455-463
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Tsai Fei-Jan,Lee Min,Liu Hsiang Chun

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference15 articles.

1. Critical Heat Flux (CHF) Phenomena on a Downward Facing Curved Surface, NUREG/CR-6507;Cheung,1997

2. Critical Heat Flux (CHF) Phenomena on a Downward Facing Curved Surface. Effects of Thermal Insulation, NUREG/CR-5534;Cheung,1998

3. CHF Experiments for External Vessel Cooling Using 2-D Slice Test Section, Presented at Severe Accident Management Study on Nuclear Installations (SAMSON) Seminar on In-Vessel Retention Strategy for High-Power Reactors;Chang,2002

4. Dinh, T.N., Tu, T.P., Salmassi, T., Theofanous, T.G. 2003. Limits of coolability in the AP1000-related ULPU-2400 Configuration V facility. In: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea.

5. Esmaili, H., Khatib-Rahbar, M. 2004. Analysis of in-vessel retention and ex-vessel fuel coolant interaction for AP1000. Energy Research Inc, ERI/NRC 04–201, NUREG/CR-6849.

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