Electron Microscopic Examination of Irradiated TRISO Coated Particles of Compact 6-3-2 of AGR-1 Experiment

Technical Report · Sat Dec 01 04:00:00 EST 2012

DOI:https://doi.org/10.2172/1364097· OSTI ID:1364097

Van Rooyen, Isabella Johanna ^[1]; Demkowicz, Paul Andrew ^[1]; Riesterer, Jessica Lori ^[1]; Miller, Brandon Douglas ^[1]; Janney, Dawn Elizabeth ^[1]; Harp, Jason Michael ^[1]; Ploger, Scott Arden ^[1]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)

The electron microscopic examination of selected irradiated TRISO coated particles of the AGR-1 experiment of fuel compact 6-3-2 are presented in this report. Compact 6-3-2 refers to the compact in Capsule 6 at level 3 of Stack 2. The fuel used in capsule 6 compacts, are called the “baseline” fuel as it is fabricated with refined coating process conditions used to fabricate historic German fuel, because of its excellent irradiation performance with UO2 kernels. The AGR-1 fuel is however made of low-enriched uranium oxycarbide (UCO). Kernel diameters are approximately 350 µm with a U-235 enrichment of approximately 19.7%. Compact 6-3-2 has been irradiated to 11.3% FIMA compact average burn-up with a time average, volume average temperature of 1070.2°C and with a compact average fast fluence of 2.38E21 n/cm

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1364097
• Report Number(s): INL/EXT--11-23911
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ENRICHED URANIUM
FUELS
KERNELS
NGNP
Next Generation Nuclear Plant Project
SURFACE COATING
URANIUM 235
URANIUM DIOXIDE
VHTR
Very High Temperature Reactor