Experimental study of free flow and heat transfer in narrow vertical rectangular channels
Creators
- 1. Turkish Atomic Energy Authority, Cekmece Nuclear Research and Training Center, Istanbul (Turkey)
Description
Free convection cooling of electronic boards and vertical channel type structures of systems in the facilities of some installations, in the abnormal working situations, is becoming important recent years. Plate type fueled pool type research reactors, such TR-2 reactor of CHNAEM have very narrow (2.1 mm width) vertical cooling channels. In case of an accident or a loss of cooling event, the heat transfer in this channels should be accomplished by natural circulation. The adequacy of this cooling should be proved for safety consideration. A simple experimental setup was constructed to simulate a TR-2 cooling channel. Plate powers and channel widths were the parameters changed. Dummy fuel plates were heated by DC current and temperature measurements were done by Cu-Constantan thermocouples located inside the channel and around it. Average Nu and Ra numbers were calculated for the channel and they are compared with the numerical results. Working fluid was air
Availability note (English)
Available from INIS in electronic form; Also available from Turkish Atomic Energy AuthorityFiles
36003504.pdf
Files
(249.6 kB)
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Additional details
Additional titles
- Original title (Turkish)
- Dar ve duesey kanallarda akis ve isi transferinin deneysel etuedue
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- INIS-TR--0085
INIS
- Country of Publication
- Turkey
- Country of Input or Organization
- Turkey
- INIS RN
- 36003504
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; FUEL PLATES; HEAT TRANSFER; HOT CHANNEL; HOT CHANNEL FACTOR; NATURAL CONVECTION; REACTOR CHANNELS; REACTOR COOLING SYSTEMS; REACTOR EXPERIMENTAL FACILITIES; TR-2 REACTOR
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; DATA; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT TRANSFER; INFORMATION; MASS TRANSFER; NUMERICAL DATA; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- TR 334