Published 1977
| Version v1
Report
Restricted
In-reactor cladding breach of EBR-II driver-fuel elements
Description
Knowledge of performance and minimum useful element lifetime of Mark-II driver-fuel elements is required to maintain a high plant operating capacity factor with maximum fuel utilization. To obtain such knowledge, intentional cladding breach has been obtained in four run-to-cladding-breach Mark-II experimental driver-fuel subassemblies operating under normal conditions in EBR-II. Breach and subsequent fission-product release proved benign to reactor operations. The breaches originated on the outer surface of the cladding in the root of the restrainer dimples and were intergranular. The Weibull distribution of lifetime accurately predicts the observed minimum useful element lifetime of 10 at.% burnup, with breach ensuing shortly thereafter
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 22 p.
- Report number
- CONF-770641--4
Conference
- Title
- Conference on radiation effects in breeder reactor structural materials.
- Dates
- 19 - 23 Jun 1977.
- Place
- Scottsdale, Arizona, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8348072
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; EBR-2 REACTOR; FUEL CANS; FUEL ELEMENT FAILURE; FUEL ELEMENTS; PERFORMANCE TESTING; REACTOR OPERATION
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; OPERATION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; TESTING