Published 1979
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Fuel rod response during LOFT Test L2-2
Description
The Loss-of-Fluid Test (LOFT) Facility is providing unique data on the response of a nuclear reactor to a loss-of-coolant accident (LOCA). The data are being used to assess the accuracy of the computer codes used in reactor safety analysis. The first LOFT nuclear test, Test L2-2, was a cold leg break LOCA at a peak linear power of 26.25 kW/m. The paper briefly describes the LOFT core, discusses fuel rod response during Test L2-2, and compares the data with the test prediction
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
10488195.pdf
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(106.9 kB)
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Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- CONF-790602--22
Conference
- Title
- ANS annual meeting.
- Dates
- 3 - 8 Jun 1979.
- Place
- Atlanta, GA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10488195
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LOFT REACTOR; LOSS OF COOLANT; REACTOR EXPERIMENTAL FACILITIE; REACTOR OPERATION; SIMULATION
- Descriptors DEC
- ACCIDENTS; OPERATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS