Development of an empirical correlation for the onset of flow instability in narrow rectangular channels-Reference-Cited by-同舟云学术

Development of an empirical correlation for the onset of flow instability in narrow rectangular channels

Published:2021-04 Issue: Volume:375 Page:111090
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ha Tae Wook,Bae Sung Won,Park Jong-Pil,Jo Daeseong,Yun Byong-Jo,Jun Jeong Jae

Funder

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference20 articles.

1. ONB, OSV, and OFI for subcooled flow boiling through a narrow rectangular channel heated on one-side;Al-Yahia;Int. J. Heat Mass Transf.,2018

2. Review of two-phase flow instability;Boure;Nucl. Eng. Des.,1973

3. Bowring, W.R., 1962. Physical Model of Bubble Detachment and Void Volume in Subcooled Boiling. OECD Halden Reactor Project Report No. HPR-10.

4. Criteria for Onset of Flow Instability in heated vertical narrow rectangular channels at low pressure: an assessment study;Ghione;Int. J. Heat Mass Transf.,2017

5. Improvement of the MARS subcooled boiling model for a vertical upward flow;Ha;Nucl. Eng. Technol.,2019

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1. Experimental investigation on steam-water flow patterns in a vertical narrow rectangular channel utilizing conductance scanning measurement;International Journal of Heat and Mass Transfer;2024-05

2. Comparative study of constitutive relations implemented in RELAP5 and TRACE – Part I: Methodology & wall friction;Nuclear Engineering and Technology;2022-09

3. Two-phase flow boiling instabilities: A review;Annals of Nuclear Energy;2022-08