Published December 1977
| Version v1
Report
Open
Postirradiation examination results for the Irradiation Effects Test Series IE-ST-2, Rod IE-002
Description
A postirradiation examination was conducted on a zircaloy-clad, UO2-fueled, pressurized water reactor (PWR) type rod which had been tested in the Power Burst Facility as part of the Irradiation Effects Test Series of the Thermal Fuels Behavior Program. The fuel rod, previously irradiated to a burnup of 15,800 MWd/t was subjected to a power ramp from 28 to 55 kW/m peak power at an average ramp rate of 4 kW/m/min. Posttest fuel restructuring and relocation, fission product redistribution, and fuel rod cladding deformation were evaluated and analyzed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.Files
9383611.pdf
Files
(5.4 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:6bd23dbd29ae50d766f532c6388d9612
|
5.4 MB | Preview Download |
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 42 p.
- Report number
- TREE-NUREG--1177
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9383611
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DEFORMATION; FUEL ELEMENTS; FUEL RODS; IRRADIATION; PERFORMANCE; PERFORMANCE TESTING; PWR TYPE REACTORS
- Descriptors DEC
- REACTOR COMPONENTS; REACTORS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS