Liquid film behavior and heat-transfer mechanism near the rewetting front in a single rod air–water system
Author:
Affiliation:
1. Nuclear Safety Research Center, Japan Atomic Energy Agency (JAEA), Ibaraki, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2019.1659872
Reference10 articles.
1. Atomic Energy Society of Japan. 2003 standard for assessment of fuel integrity under anticipated operational occurrence in BWR power plants; 2003. (Report no. Technical Report on AESJ-SC-P002:2003). [In Japanese].
2. Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs
3. Rewetting front propagation under anticipated operational occurrences for boiling water reactors – development of two-dimensional analytical model
4. Heat conduction analyses on rewetting front propagation during transients beyond anticipated operational occurrences for BWRs
5. Measurements of liquid film and droplets of annular two-phase flow on a rod-bundle geometry with spacer
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