Measurement of Local Void Fraction of Air-Water Flow in an 8 × 8 Rod Bundle Using High-Resolution Gamma-Ray Tomography-Reference-Cited by-同舟云学术

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Measurement of Local Void Fraction of Air-Water Flow in an 8 × 8 Rod Bundle Using High-Resolution Gamma-Ray Tomography

Published:2023-05-11 Issue:12 Volume:209 Page:1898-1913
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Ahn Taehwan¹^ORCID,Diaz Julio¹,Adams Robert¹²,Petrov Victor¹²³^ORCID,Manera Annalisa¹²³^ORCID

Affiliation:

1. University of Michigan, Department of Nuclear Engineering & Radiological Sciences, Ann Arbor, Michigan

2. ETH Zürich, Department of Mechanical and Process Engineering, Zürich, Switzerland

3. Paul Scherrer Institut (PSI), Laboratory for Reactor Physics and Thermal-Hydraulics (LRT), Villigen, Switzerland

Funder

U.S. Nuclear Regulatory Commission

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2023.2197680

Reference28 articles.

1. Flow pattern transition for gas-liquid flow in a vertical rod bundle

2. Modeling and measurement of interfacial area concentration in two-phase flow

3. Flow Regime Identification Under Adiabatic Upward Two-Phase Flow in a Vertical Rod Bundle Geometry

4. Sensitivity analysis of bubble size and probe geometry on the measurements of interfacial area concentration in gas-liquid two-phase flow

5. Experimental study of interfacial area transport in air–water two phase flow in a scaled 8×8 BWR rod bundle

Cited by 2 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. Validation of a three-dimensional two-phase code, CUPID, using a rod-bundle boiling test facility, SIRIUS-3D;Annals of Nuclear Energy;2024-12

2. Validation of a Three-Dimensional Two-Phase Code, Cupid, Using a Rod-Bundle Boiling Test Facility, Sirius-3d;2024

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