Data Compilation for AGR-2 B&W UO2 Coated Particle Batch G73H-10-93085B
Coated particle fuel batch G73H-10-93085B was produced by the Babcock and Wilcox Company (B&W) for use as UO₂ fuel for the Advanced Gas Reactor Fuel Development and Qualification Program’s AGR-2 irradiation test. Batch G73H-10-93085B is a single batch of TRISO-coated 500 μm nominal diameter 10% low enrichment uranium oxide kernels (LEU). The TRISO-coatings consist of a ~50% dense carbon buffer layer (100 μm nominal thickness) followed by a dense inner pyrocarbon layer (40 μm nominal thickness) followed by a SiC layer (35 μm nominal thickness) followed by another dense outer pyrocarbon layer (40 μm nominal thickness). Argon was added to the hydrogen fluidization gas during SiC deposition. The AGR-2 Fuel Specification (INL SPC-923) provides the requirements necessary for acceptance of the fuel manufactured for the AGR-2 irradiation test. The bulk of the kernels and coated particle acceptance testing was performed at B&W and is not contained in this report. B&W samples NP-B8488, NP-B8489, and NP-B8490 (all from batch G73H-10-93085B) were sent to ORNL for characterization and compacting. These samples were composited and renamed LEU10. Samples were then riffled for supplemental characterization. The procedures for the limited characterization and qualification of the particles performed at ORNL are outlined in ORNL product inspection plan AGR-CHAR-PIP-09. The BAFo equivalent optical anisotropies of the inner and outer pyrocarbon layers are reported on Inspection Report Form IRF-09, with a determination as to whether the particle batch satisfied the specified parameters for this property. The batch was found to satisfy the AGR-2 Fuel Specification SPC-923, Rev. 1 for IPyC and OPyC anisotropy. Also provided in this data package are data on the true BAFo, average particle weight, and SiC soot inclusion defect fraction. True BAFo is calculated as (1+N)/(1-N), where N is the diattenuation. This differs from equivalent BAFo = 1+3N, which is the calculation used by the fuel specification to allow comparison to historical measurements. Three SiC inclusions were found in a sample of 3510 particles. This corresponds to a defect fraction of <2.3E-3 at 95% confidence. One of these inclusions was of unusual appearance and was determined to contain molybdenum using energy dispersive x-ray analysis.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1649219
- Report Number(s):
- ORNL/TM-2009/255; TRN: US2202177
- Country of Publication:
- United States
- Language:
- English
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