Validation of interfacial area concentration model for simulating bubbly and cap/slug flow behaviors in large diameter pipes using LSTF, ATLAS, and horizontal pipe experiment data-Reference-Cited by-同舟云学术

Validation of interfacial area concentration model for simulating bubbly and cap/slug flow behaviors in large diameter pipes using LSTF, ATLAS, and horizontal pipe experiment data

Published:2020-10 Issue: Volume:128 Page:103499
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Heo Jaeseok,Yoon Seung Hyun,Kim Kyung Doo,Ha Kwi-Seok,Hibiki Takashi

Funder

Korea Hydro & Nuclear Power Co., Ltd.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference37 articles.

1. KAERI integral effect test program and the ATLAS design;Baek;Nucl. Technol.,2005

2. The physical closure laws in the CATHARE code;Bestion;Nucl. Eng. Des.,1990

3. Personal Communication about Loop Seal Clearing Prediction;Bestion,2019

4. “Observation and Correlation of Flow Pattern Transition in Horizontal, Co-current Gas-Liquid Flow,” Two-phase Transport and Reactor Safety;Choe,1978

5. “The Bubbly-Slug Transition in a High Velocity Two Phase Flow,” Technical Report No. 5003-29;Griffith,1964

Cited by 9 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. Sub-regimes of horizontal gas–liquid intermittent flow: State-of-the-art and future challenges;Experimental Thermal and Fluid Science;2025-01

2. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

3. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

4. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

5. Unified two-component interfacial area concentration model for narrow channel two-phase flow;International Journal of Multiphase Flow;2023-06