Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle
Author:
Affiliation:
1. Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2023.2223588
Reference20 articles.
1. Investigation of Water-Vapor Two-Phase Flow Characteristics in a Tight-Lattice Core by Large-Scale Numerical Simulation, (I)
2. A numerical simulation method for molten material behavior in nuclear reactors
3. Ohnuki A, Kamo H, Akimoto H. Improvement of multi-dimensional two-fluid model code ACE-3D and application to thermal-hydraulic analysis of water pool for passive residual heat removal. Ibaraki (Japan): JAERI-Data/Code;1999 p. 99–038. in Japanese.
4. Development of JAEA Advanced Multi-Physics Analysis Platform for Nuclear Systems
5. Experimental study of interfacial area transport in air–water two phase flow in a scaled 8×8 BWR rod bundle
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