Observation on the Irradiation Behavior of U-Mo Alloy Dispersion Fuel

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
2000 International RERTR Meeting

Observation on the Irradiation Behavior of U-Mo Alloy Dispersion Fuel

Gerard L. Hofman, Mitchell K. Meyer
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439

Jong-Man Park
Korea Atomic Energy Research Institute
150 Dukjin-Dpong, Yusong-Ku
Taejon, South Korea 305-600

ABSTRACT

Initial results from the postirradiation examination of high-density dispersion fuel test RERTR-3 are discussed. The U-Mo alloy fuels in this test were irradiated to 40% U-235 burnup at temperature ranging from 140ºC to 240ºC. Temperature has a significant effect on overall swelling of the test plates. The magnitude of the swelling appears acceptable and no unstable irradiation behavior is evident.

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Contact:
Dr. Gerard Hofman
Senior Metallurgist
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439 USA

Phone: (630) 252-6683
Fax: (630) 252-5161

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	ARGONNE NATIONAL LABORATORY, Nuclear Engineering Division, RERTR Department 9700 South Cass Ave., Argonne, IL 60439-4814 A U.S. Department of Energy laboratory managed by UChicago Argonne, LLC

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

Abstracts and Available Papers Presented at the2000 International RERTR Meeting

Observation on the Irradiation Behavior of U-Mo Alloy Dispersion Fuel

Abstracts and Available Papers Presented at the
2000 International RERTR Meeting