Fundamental metallurgical aspects of axial splitting in zircaloy cladding
Description
Fundamental metallurgical aspects of axial splitting in irradiated Zircaloy cladding have been investigated by microstructural characterization and analytical modeling, with emphasis on application of the results to understand high-burnup fuel failure under RIA situations. Optical microscopy, SEM, and TEM were conducted on BWR and PWR fuel cladding tubes that were irradiated to fluence levels of 3.3 x 1021 n cm-2 to 5.9 x 1021 n cm-2 (E > 1 MeV) and tested in hot cell at 292--325 C in Ar. The morphology, distribution, and habit planes of macroscopic and microscopic hydrides in as-irradiated and posttest cladding were determined by stereo-TEM. The type and magnitude of the residual stress produced in association with oxide-layer growth and dense hydride precipitation, and several synergistic factors that strongly influence axial-splitting behavior were analyzed. The results of the microstructural characterization and stress analyses were then correlated with axial-splitting behavior of high-burnup PWR cladding reported for simulated-RIA conditions. The effects of key test procedures and their implications for the interpretation of RIA test results are discussed
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00754479; PURL: https://www.osti.gov/servlets/purl/754479-PKtNKP/webviewable/Files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- ANL/ET/CP--101429
Conference
- Title
- International Topical Meeting on Light Water Reactor Fuel Performance
- Dates
- 10-13 Apr 2000
- Place
- Park City, UT (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 31042101
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FUEL CANS; FUEL ELEMENT FAILURE; MICROSTRUCTURE; PHYSICAL RADIATION EFFECTS; POST-IRRADIATION EXAMINATION; PWR TYPE REACTORS; ZIRCALOY
- Descriptors DEC
- ALLOYS; ENRICHED URANIUM REACTORS; POWER REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Contract/Grant/Project number
- W-31109-ENG-38
- Funding organization
- US Department of Energy (United States)