Microstructure of the Irradiated U3Si2/Al Silicide Dispersion Fuel

Journal Article · Thu Dec 01 04:00:00 EST 2011 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2011.07.030· OSTI ID:1032885

Gan, J; Keiser, Jr, D D; Miller, B D; Jue, J -F; Robinson, A B; Medvedev, P G; Wachs, D M

The silicide dispersion fuel of U3Si2/Al is recognized as the best performance fuel for many nuclear research and test reactors with up to 4.8 gU/cm3 for low-enriched uranium fuel (LEU, 235U < 20%). An irradiated U3Si2/Al dispersion fuel (235U {approx}75%) from the high flux side of a fuel plate (U0R040) from the Reduced Enrichment for Research and Test Reactors (RERTR)-8 test was characterized using transmission electron microscopy (TEM). The fuel was irradiated in the Advanced Test Reactor (ATR) for 105 days. The average irradiation temperature and fission density of the U3Si2 fuel particles for the TEM sample are estimated to be approximately 110 C and 5.4 x 1027 f/m3. The characterization was performed using a 200 kV TEM. Detailed microstructural information along with composition analysis is obtained. The results and their implication on the performance of the U3Si2/Al silicide dispersion fuel are discussed.

• Research Organization: Idaho National Laboratory (INL)
• Sponsoring Organization: DOE - NE
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1032885
• Report Number(s): INL/JOU-11-21283
• Journal Information: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1 - 3 Vol. 419; ISSN 0022-3115; ISSN JNUMAM
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
FISSION
FUEL PARTICLES
FUEL PLATES
IRRADIATION
MICROSTRUCTURE
PERFORMANCE
RESEARCH AND TEST REACTORS
SILICIDES
TEM
TEST REACTORS
TRANSMISSION ELECTRON MICROSCOPY
URANIUM
bubble
fission
fuel
interaction
microstructure