Experimental assessment of the Chexal-Lellouche void correlation for low-flow conditions and tight-lattice geometry
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:76162
The Chexal-Lellouche correlation succeeded in correlating a broad range of experimental conditions relevant to nuclear reactor thermal-hydraulic analysis. To further the existing assessment of the Chexal-Lellouche void correlation for low-flow conditions and its applicability to tight triangular lattices typical of light water high-conversion reactor (LWHCR) fuel assemblies, void fraction measurements were undertaken using the NEPTUN-III test facility and were compared with predicted values. In addition, these data were also used to test the MHI correlation, whose authors claimed a better performance than Chexal-Lellouche`s.
- OSTI ID:
- 76162
- Report Number(s):
- CONF-940602--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 70; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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