DRAG COEFFICIENTS FOR FUEL-ELEMENT SPACERS
Journal Article
·
· Nucleonics (U.S.) Ceased publication
OSTI ID:4004545
The reactor fuel geometry is considered in which a bundle of fuel pins or rods are separated by spacers, and the coolant flow is parallel to the bundle axis. For this type of geometry, the pressure loss of the coolant across several types of spacers is calculated. Various arrangements of circular wires, lenticular wires, and honeycomb grids, as well as spiral wire wrapping around each pin or rod, are analyzed. (T.F.H.)
- Research Organization:
- BelgoNucleaire S.A., Brussels
- NSA Number:
- NSA-15-019524
- OSTI ID:
- 4004545
- Journal Information:
- Nucleonics (U.S.) Ceased publication, Journal Name: Nucleonics (U.S.) Ceased publication Vol. Vol: 19: No. 6; ISSN NUCLA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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