Post-irradiation analysis of low enriched U-Mo/Al dispersions fuel miniplate tests, RERTR 4 & 5.
Conference
·
OSTI ID:944023
Interpretation of the post irradiation data of U-Mo/Al dispersion fuel mini plates irradiated in the Advanced Test Reactor to a maximum U-235 burn up of 80% are presented. The analyses addresses fuel swelling and porosity formation as these fuel performance issues relate to fuel fabrication and irradiation parameters. Specifically, mechanisms involved in the formation of porosity observed in the U-Mo/Al interaction phase are discussed and, means of mitigating or eliminating this irradiation phenomenon are offered.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- DE-AC02-06CH11357
- OSTI ID:
- 944023
- Report Number(s):
- ANL/NE/CP-114893; TRN: US0900496
- Resource Relation:
- Conference: 26th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), 2004; Nov. 7, 2004 - Nov. 12, 2004; Vienna, Austria
- Country of Publication:
- United States
- Language:
- ENGLISH
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