Experimental test results of multi-channel test rig of T1 test section, 4
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
The multi-channel test rig (T1-M) of the fuel stack test section in the helium engineering demonstration loop (HENDEL) is a large-scale experimental facility which simulates one fuel column of the HTTR core. A crossflow test was carried out using the T1-M. The objectives of this test are to investigate the thermal and hydraulic characteristics in the fuel stack under the conditions that produced the crossflow through a gap from the outside of the graphite blocks into twelve coolant channels: the crossflow was forcibly produced by a parallel gap situated between the third and fourth blocks from the top of those in the heated section mounted in the vertical direction. Crossflow rate were about a half of the total flow rate of helium gas in T1-M for heated flow. A decrease of the gap width raised the crossflow rates in outer channels (No.7∼12) and also reduced those in inner channels (No.1∼6). It was found that the crossflow affected flow redistributions in the channels and temperature distributions of the fuel rods. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
22009921.pdf
Files
(1.3 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:e84adff7f0978bc391758a078c125d93
|
1.3 MB | Preview Download |
Additional details
Additional titles
- Subtitle (English)
- Crossflow test in parallel gap
Publishing Information
- Imprint Pagination
- 37 p.
- Report number
- JAERI-M--90-118
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 22009921
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CROSSFLOW SYSTEMS; EXPERIMENTAL DATA; FLOW RATE; FUEL RODS; GRAPHITE; HEAT TRANSFER; HELIUM; HIGH TEMPERATURE; HTTR REACTOR; HYDRAULICS; REACTOR CHANNELS; REACTOR EXPERIMENTAL FACILITIE; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- CARBON; DATA; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INFORMATION; NONMETALS; NUMERICAL DATA; RARE GASES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS