Rod deformation and cladding reactions in a PWR fuel rod cluster: results of test PCM-5
Description
The Thermal Fuels Behavior Program of EG and G Idaho, Inc., has conducted irradiation tests since 1975 for the U.S. Nuclear Regulatoy Commission to determine the effects of operation in overpower or undercooling modes on pressurized water reactor (PWR) type fuel rods. Highly instrumented single-rod tests, performed in the power-cooling-mismatch (PCM) test series, have produced extensive data on the coolant thermal-hydraulic conditions required to produce departure from nuclear boiling (DNB) and the consequences to Zircaloy cladding integrity of sustained film boiling operation. Test PCM-5, the first nine-rod cluster test of the PCM test series, (a 3 x 3 rod array within a flow shroud) was performed in May 1978 to (a) assess film boiling behavior of a fuel rod in a configuration representative of power reactor fuel bundles, and (b) to determine whether rod-to-rod DNB propagation or failure propagation would occur. Test results are discussed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 3 p.
- Report number
- DOE/TIC--10111
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10488076
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DEFORMATION; DEPARTURE NUCLEATE BOILING; FILM BOILING; FUEL ELEMENT CLUSTERS; FUEL ELEMENT FAILURE; PWR TYPE REACTORS; SIMULATION
- Descriptors DEC
- ACCIDENTS; BOILING; FUEL ASSEMBLIES; NUCLEATE BOILING; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS