POST-IRRADIATION ANALYSIS OF LOW ENRICHED U-Mo/A1 DISPERSIONS FUEL MINIPLATE TESTS, RERTR 4 & 5

RERTR
Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne

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Abstracts and Available Papers Presented at the
2004 International RERTR Meeting

POST-IRRADIATION ANALYSIS OF LOW ENRICHED U-Mo/A1 DISPERSIONS FUEL MINIPLATE TESTS, RERTR 4 & 5

G.L. Hofman, M.R. Finlay and Y.S. Kim

Argonne National Laboratory Nuclear Engineering Division Argonne, Illinois 60439

ABSTRACT

Interpretation of the post irradiation data of U-Mo/A1 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/A1 interaction phase are discussed and, means of mitigating or eliminating this irradiation phenomenon are offered.

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Last modified on July 29, 2008 11:32 +0200

Abstracts and Available Papers Presented at the2004 International RERTR Meeting

POST-IRRADIATION ANALYSIS OF LOW ENRICHED U-Mo/A1 DISPERSIONS FUEL MINIPLATE TESTS, RERTR 4 & 5

Abstracts and Available Papers Presented at the
2004 International RERTR Meeting