Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC-Reference-Cited by-同舟云学术

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Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC

Published:2016-03 Issue: Volume:89 Page:50-55
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Park Rae-Joon,Ha Kwang-Soon,Kim Hwan-Yeol

Funder

National Research Foundation of Korea

Ministry of Science, ICT and Future Planning

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Limits of Coolability in the AP1000-Related ULPU-2400 Configuration V Facility, NURETH-10, Seoul, Korea;Dinh,2003

2. Two-phase natural circulation flow in AP-1000 in-vessel retention-related ULPU-V facility experiments;Dinh,2004

3. Analysis of In-Vessel Retention and Ex-Vessel Fuel Coolant Interaction, NUREG/CR-6849, ERI/NRC 04-241;Esmaili,2004

4. In-vessel Retention Workshop on Severe Accident Management of Korea Next Generation Reactor;KEPCO,1998

5. Korean Next Generation Reactor Standard Safety Analysis Report;KEPCO,2001

Cited by 12 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Variation of heat load due to in-vessel debris bed in IVR condition;Progress in Nuclear Energy;2023-08

2. Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal-Hydraulic System Analysis Code;International Journal of Energy Research;2023-03-03

3. A review of the assessment of severe accident management guidelines and actions through analytical simulations;Annals of Nuclear Energy;2023-01

4. Influence of an in-vessel debris bed on the heat load to a reactor vessel under an IVR condition;Nuclear Engineering and Technology;2023-01

5. Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate;Nuclear Engineering and Technology;2022-01

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