Void fraction estimation within rod bundles based on three-fluid model and comparison with x-ray CT void data-Reference-Cited by-同舟云学术

Void fraction estimation within rod bundles based on three-fluid model and comparison with x-ray CT void data

Published:1990-06 Issue:2-3 Volume:120 Page:203-212
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Mitsutake T.,Morooka S.,Suzuki K.,Tsunoyama S.,Yoshimura K.

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

Reference26 articles.

1. Multi-fluid modeling of annular two-phase flow;Saito;Nucl. Engrg. Des.,1978

2. Critical power analysis with multi-fluid model;Terasaka,1986

3. The calculation of dryout in a rod bundle;Whalley;Int. J. Multiphase Flow,1977

4. Theoretically based predictions of critical heat flux in rod bundles;Weisman,1985

5. Development of subchannel analysis code based on the three-fluid model;Sugawara,1988

Cited by 26 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. Measurement of Local Void Fraction of Air-Water Flow in an 8 × 8 Rod Bundle Using High-Resolution Gamma-Ray Tomography;Nuclear Technology;2023-05-11

2. Void fractions in a rod bundle geometry at high pressure–part Ⅰ: Experimental study;International Journal of Multiphase Flow;2020-01

3. Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6 × 6 rod bundle;International Journal of Heat and Mass Transfer;2019-12

4. Constitutive equations for vertical upward two-phase flow in rod bundle;International Journal of Heat and Mass Transfer;2018-12

5. Measurements using X‐ray attenuation vertical distribution of the void fraction for different flow regimes in a horizontal pipe;Nuclear Engineering and Design;2018-09