CCFL in hot legs and steam generators and its prediction with the CATHARE code-Reference-Cited by-同舟云学术

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CCFL in hot legs and steam generators and its prediction with the CATHARE code

Published:1995-09-01 Issue: Volume: Page:
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Author:

Geffraye G,Bazin P,Pichon P¹

Affiliation:

1. CEA/DRN/STR, Grenoble (France)

Publisher

Office of Scientific and Technical Information (OSTI)

Cited by 12 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. Experimental Investigations and Numerical Studies of Two-Phase Countercurrent Flow Limitation in a Pressurized Water Reactor: A Review;Energies;2023-02-02

2. A new correlation for CCFL at full scale PWR excluding the Hutze effect in UPTF data;Nuclear Engineering and Design;2021-11

3. Characterization and prediction of flow-conditions in the hot-leg of PWR during loss of coolant accident;Nuclear Engineering and Design;2020-04

4. Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes;Journal of Nuclear Engineering and Radiation Science;2018-05-16

5. Droplets entrainment ratio in a PWR hot-leg pipe geometry;Nuclear Engineering and Design;2018-04

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