Edge blockage in a 19-pin sodium-cooled bundle
Description
To assess the effect of partial flow blockages on the local temperature distributions in LMFBR fuel assemblies, several experiments have been carried out at the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility at the Oak Ridge National Laboratory. Two kinds of flow blockages have been investigated: (1) six-channel internal blockage for which the blocked channels are not adjacent to the duct wall, and (2) 14-channel edge blockage for which some of the blocked channels are adjacent to the wall. The larger edge blockage is generally more severe than the internal blockage due to higher temperature rises in the wake behind the blockage. The experimental results on the edge blockage are analyzed and presented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
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Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- CONF-771120--8
Conference
- Title
- Winter annual meeting of the American Society of Mechanical Engineers.
- Dates
- 27 Nov - 2 Dec 1977.
- Place
- Atlanta, GA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9373823
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONFIGURATION; FLOW BLOCKAGE; FUEL ASSEMBLIES; FUEL PINS; HEAT TRANSFER; HYDRAULICS; LMFBR TYPE REACTORS; MOCKUP; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- BREEDER REACTORS; DISTRIBUTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; STRUCTURAL MODELS