Published 1978
| Version v1
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Effect of rod surface thermocouples on transient critical heat flux
Description
Tests to determine CHF times during loss of coolant experiments ''Blowdown'' were conducted on two 25-rod simulated fuel bundles. The tests were conducted at normal PWR conditions and geometry with power levels of 23, 39 and 52 kW/m. The tests show that thermocouples attached to the surface do not significantly affect time-to-CHF in the rod bundles tested. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
10433152.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- INIS-mf--4588
Conference
- Title
- ENS/ANS international topical meeting on nuclear power reactor safety.
- Dates
- 16 - 19 Oct 1978.
- Place
- Brussels, Belgium.
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- Belgium
- INIS RN
- 10433152
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BLOWDOWN; CRITICAL HEAT FLUX; FUEL RODS; LOFT REACTOR; ROUGHNESS; SIMULATION; THERMOCOUPLES
- Descriptors DEC
- FUEL ELEMENTS; HEAT FLUX; MEASURING INSTRUMENTS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SURFACE PROPERTIES; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs.