Published 1970
| Version v1
Miscellaneous
Open
Experimental determination of contact heat resistance between uranium dioxide and cladding
Creators
- 1. Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)
Description
The objective of this work was studying thermal contact resistance between fuel and cladding under different conditions similar to reactor operating conditions in order to avoid overheating that could cause damage. According to experimental data, variation of contact heat resistance was analyzed dependent on the neutron flux. Using calculated values of fuel pellets radial expansion, dependence of heat contact resistance is given as a function of gap dimensions at constant temperature
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCAFiles
38085307.pdf
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(277.1 kB)
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Additional details
Additional titles
- Original title (Serbian)
- Eksperimentalno odredjivanje toplotnog kontaktnog otpora izmedju uranijum dioksida i kosuljice
Publishing Information
- Publisher
- Society for Electronics,Telecommunications, Automation, and Nuclear Engineering
- Imprint Place
- Belgrade (Yugoslavia)
- Imprint Pagination
- 8 p.
- Report number
- INIS-RS--1049
Conference
- Title
- ETAN 14. - Conference
- Original Conference Title
- Zbornik radova 14. Konferencija za ETAN
- Dates
- 8-11 Jun 1970
- Place
- Sarajevo (Yugoslavia)
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Serbia
- INIS RN
- 38085307
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; FUEL PELLETS; HEAT FLUX; HEATING; NEUTRON FLUX; THERMAL ANALYSIS
- Descriptors DEC
- DEPOSITION; PELLETS; RADIATION FLUX; SURFACE COATING
Optional Information
- Notes
- 5refs, 4 figs.