Published April 1983
| Version v1
Report
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Studsvik Over-Ramp Project. Final report
Description
A total of thirty-nine PWR design fuel rods have been ramp tested under fast power increase (100 W/cm x min) in the Studsvik R2 test reactor after base irradiations in the Obrigheim and BR-3 power reactors. Burnup levels tested ranged from 12 to 31 MWd/kg U. Failure thresholds have been established within particular groups of rods having nearly identical design and base irradiation history. The failure thresholds appear to lie between a lower value of 420 W/cm and 480 W/cm at burnups around 20 MWd/kg. Differences in design and operating parameters have provided differences in observed rod performance
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A09/MF A01; 1 as DE83902264.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 176 p.
- Report number
- EPRI-NP--3007
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14787167
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; FISSION PRODUCT RELEASE; FUEL CANS; FUEL ELEMENT FAILURE; FUEL RODS; MICROSTRUCTURE; PERFORMANCE TESTING; PWR TYPE REACTORS; REACTOR SAFETY; TRANSIENT OVERPOWER ACCIDENTS; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; FUEL ELEMENTS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; TESTING; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS