On CCFL at a PWR Hot-Leg Pipe Geometry and Comparison Between Results in COLLIDER 1/4th- and Kobe 1/15th-Scaled Facilities-Reference-Cited by-同舟云学术

On CCFL at a PWR Hot-Leg Pipe Geometry and Comparison Between Results in COLLIDER 1/4th- and Kobe 1/15th-Scaled Facilities

Published:2018-08-22 Issue:1-2 Volume:193 Page:147-159
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Al Issa S.¹^ORCID,Murase M.²,Tomiyama A.³,Hayashi K.³,Macián-Juan R.¹

Affiliation:

1. Technical University Munich, Institute of Nuclear Engineering, Faculty of Mechanical Engineering, Boltzmannstrasse 15, 85748 Garching b. Muenchen, Germany

2. Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan

3. Kobe University, 1-1 Rokkodai, Nada-ku, Kobe-shi, Hyogo 657-8501, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2018.1489627

Reference19 articles.

1. Experimental and numerical investigation of counter-current stratified flows in horizontal channels

2. A study on the stratified horizontal counter-current two-phase flow

3. Experimental Study of Counter-Current Two-Phase Flow in Horizontal Tube Connected to Inclined Riser

4. Prediction of counter-current flow limitation at hot leg pipe during a small-break LOCA

5. Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling (I) Air-Water Tests for 1/15-Scale Model of a PWR Hot Leg

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

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. Experimental Investigations and Numerical Studies of Two-Phase Countercurrent Flow Limitation in a Pressurized Water Reactor: A Review;Energies;2023-02-02