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-Reference-Cited by-同舟云学术

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

Published:2022-01 Issue:1 Volume:54 Page:72-83
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Song Min Seop,Park Il Woong^ORCID,Kim Eung Soo,Lee Yeon-Gun^ORCID

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference17 articles.

1. In-vessel coolability and retention of a core melt;Theofanous;Nucl. Eng. Des.,1997

2. Preliminary Design of Optimized Reactor Insulator for Severe Accident Mitigation of APR1400;Heo,2007

3. The 1995 look-up table for critical heat flux in tubes;Groeneveld;Nucl. Eng. Des.,1996

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

5. Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC;Park;Ann. Nucl. Energy,2016

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3. 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

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