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Title: Data Compilation for AGR-1 Variant 1 Coated Particle Composite LEU01-47T

Technical Report ·
DOI:https://doi.org/10.2172/974595· OSTI ID:974595

This document is a compilation of characterization data for the AGR-1 baseline coated particle composite LEU01-46T, a composite of four batches of TRISO-coated 350 {micro}m 19.7% low enrichment uranium oxide/uranium carbide kernels (LEUCO). The AGR-1 TRISO-coated particles consist of a spherical kernel coated with a {approx} 50% dense carbon buffer layer (100 {micro}m nominal thickness) followed by a dense inner pyrocarbonlayer (40 {micro}m nominal thickness) followed by a SiC layer (35 {micro}m nominal thickness) followed by another dense outer pyrocarbon layer (40 {micro}m nominal thickness). The coated particles, were produced by ORNL for the Advanced Gas Reactor Fuel Development and Qualification (AGR) program to be put into compacts for insertion in the first irradiation test capsule, AGR-1. The kernels were obtained from BWXT and identified as composite (G73D-20-69302). The BWXT kernel lot G73D-20-69302 was riffled into sublots for characterization and coating by ORNL and identified as LEU01-?? (where ?? is a series of integers beginning with 01). The AGR-1 variant 1 coated particles were similar to the AGR-1 baseline coated particles with the exception that the inner pyrocarbon (IPyC) coating was deposited at {approx} 25 C higher temperature. A data compilation for the AGR-1 baseline coated particle composite LEU01-46T can be found in ORNL/TM-2006/019. Additional particle batches were coated with only buffer or buffer plus inner pyrocarbon (IPyC) layers using similar process conditions as used for the full TRISO batches comprising the LEU01-47T composite. These batches were fabricated in order to qualify that the process conditions used for buffer would produce acceptable densities as described in sections 8 and to measure the IPyC density as described in section 9. The buffer qualification batches were the same as used to qualify the baseline buffer conditions and used 350 {micro}m natural uranium oxide/uranium carbide kernels (NUCO). The NUCO kernels were obtained from BWXT and were identified as composite G73B-NU-69300. The use of NUCO surrogate kernels is not expected to significantly effect the density of the buffer coating. A confirmatory buffer-only batch using LEUCO kernels from G73D-20-69302 was coated and characterized to verify this assumption. The IPyC qualification batches used LEUCO kernels from G73D-20-69302.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Shared Research Equipment Collaborative Research Center
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
DE-AC05-00OR22725
OSTI ID:
974595
Report Number(s):
ORNL/TM-2006/020; AF3610200; NEAF260; TRN: US1002568
Country of Publication:
United States
Language:
English