Published 1979
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Nuclear fuel rod response during LOFT tests L2-2 and L2-3
Description
Comparisons of the measured fuel rod peak cladding temperatures for the first two nuclear loss-of-coolant experiments (LOCE), LOCEs L2-2 and L2-3, are presented. These LOCEs were performed in the Loss-of-Fluid Test (LOFT) facility at the Idaho National Engineering Laboratory. The LOCEs provided a basis for evaluating the effect of initial power on the maximum cladding temperatures during a large break (200%, guillotine) LOCE and identified important core thermal-hydraulic responses that influence the peak cladding temperatures
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
11513762.pdf
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Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- CONF-791103--29(Summ)
Conference
- Title
- American Nuclear Society meeting.
- Dates
- 12 - 16 Nov 1979.
- Place
- San Francisco, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11513762
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL CANS; LOFT REACTOR; LOSS OF COOLANT; REACTOR SAFETY; SIMULATION; SPATIAL DISTRIBUTION; THERMAL STRESSES
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; STRESSES; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS