Development of IVR-ERVC evaluation method and its application to the SMART-Reference-Cited by-同舟云学术

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Development of IVR-ERVC evaluation method and its application to the SMART

Published:2021-06 Issue: Volume: Page:108463
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Park Rae-Joon,Son Donggun,Kang Hyung Seok,An Sang Mo,Ha Kwang Soon

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference24 articles.

1. ANSYS Workbench Version 12.1, 2010, ANSYS Inc.

2. On the Enhancement of External Reactor Vessel Cooling of High-Power Reactors, NURETH-10;Cheung,2003

3. Correlating Equations for Laminar and Turbulent Free Convection from a Vertical Plate;Churchill;Int. J Heat Mass Transfer,1975

4. CINEMA-SMART Code Manual;CINEMA-SMART Development Team,2018

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

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1. Failure simulation of nuclear pressure vessel under LBLOCA scenarios;Nuclear Engineering and Technology;2024-07

2. Development of an on-demand flooding safety system achieving long-term inexhaustible cooling of small modular reactors employing metal containment vessel;Nuclear Engineering and Technology;2024-07

3. A Study on Boiling Heat Transfer Performance of TiO ₂ -CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface;Nuclear Technology;2024-04-11

4. Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor;Nuclear Engineering and Technology;2023-11

5. Simulations of Core Damage Progression for TMI-2 Severe Accident Using CINEMA Computer Code;Science and Technology of Nuclear Installations;2023-02-27

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