Advanced Microscopy Report on UCO Fuel Kernels from Selected AGR-1 and AGR-2 Experiments
The technical bases for the TRISO-coated particle fuel specifications used by the AGR Program during its fabrication process development and fuel qualification efforts are provided based on historical HTGR fabrication experience in the U.S. and Germany and improvements and insights gained during execution of the AGR Program. The technical bases are provided for specified properties […]
Quality Control Methods for Measurement of UCO Kernel Composition and SiC Microstructure
Quality control (QC) is critically important to tristructural-isotropic (TRISO) particle fuels owing to the complexity of and reliance on the fuel form to contain fission products during irradiation. Characterization methods for particle fuel QC have decades of history and have continued to develop as new insights into fuel performance inform revised fuel specifications and as […]
Data Compilation for AGR-3/4 Designed-to-Fail (DTF) Fuel Particle Batch LEU03-07DTF
This document is a compilation of coating and characterization data for the designed-to-fail (DTF) fuel particle batch LEU03-07DTF. LEU03-07DTF was fabricated for insertion into fuel compacts designed for the Advanced Gas Reactor Fuel Development and Qualification (AGR) program’s third irradiation test (AGR-3/4). This document also includes coating and characterization data for the associated qualification DTF […]
Data Compilation for AGR-3/4 Matrix Ring Blank Lot ARB-B1
This document is a compilation of compacting and characterization data for the matrix ring blank set ARB-B1. These ring blanks were made using a graphite/resin blend of natural and synthetic graphite flake mixed with Hexion SD-1708 novolac resin (Blend I). The Blend I material was provided to Oak Ridge National Laboratory (ORNL) by Babcock & […]
Data Compilation for AGR-3/4 Driver Particle Composite LEU03-09T
This document is a compilation of characterization data for the AGR-3/4 driver fuel coated particle composite LEU03-09T, a composite of four batches of TRISO-coated, nominally 350 {micro}m diameter, 19.7% low enrichment uranium oxide/uranium carbide kernels (LEUCO). The AGR-3/4 driver fuel particles were fabricated using the AGR-1 baseline coating conditions and consist of a spherical kernel […]
Results from ORNL Characterization of Nominal 350 ?m LEUCO Kernels (LEU03) from the BWXT G73V-20-69303 Composite
Measurements were made using optical microscopy to determine the size and shape of the LEU03 kernels. Hg porosimetry was performed to measure density. The results are summarized in Table 1-1. Values in the table are for the composite and are calculated at 95% confidence from the measured values of a random riffled sample. The LEu03 […]
AGR-2 Fuel Compact Pre-Irradiation Characterization Summary Report
This document is a summary of pre-irradiation characterization data for four of the compact lots used in the Department of Energy’s Office of Nuclear Energy (DOE-NE) Advanced Gas Reactor Fuel Development and Qualification (AGR) program second irradiation test, AGR-2. Kernels and coated particles were produced by Babcock and Wilcox (B&W) in Lynchburg Virginia. Compacts were […]
AGR-2 TRISO Fuel Post-Irradiation Examination Final Report
An array of post-irradiation exams and experiments were employed to assess the irradiation performance and high-temperature behavior of AGR-2 UCO TRISO fuel produced in an engineering-scale coater. Work was also conducted on UO2 TRISO fuel produced for comparison with the AGR UCO fuel. Emphases we replaced on enumerating the frequency of SiC layer failures (failure […]
Oxidation Testing and Examination of AGR-2 Particles
Post-irradiation examination (PIE) oxidation testing is being performed at Oak Ridge National Laboratory (ORNL) on fuel particles from the second Advanced Gas Reactor (AGR) irradiation experiment (AGR-2). Tristructural isotropic (TRISO)-coated particles containing mixed uranium carbide and uranium oxide (UCO) fuel kernels were taken from AGR-2 Compact 5-4-2 and heated in the Furnace for Irradiated TRISO […]
AGR-2 Loose Particle Heating Tests in the Furnace for Irradiated TRISO Testing
A furnace system was developed to thermally expose individual tristructural-isotropic (TRISO) coated particles to expand upon established postirradiation examination (PIE) safety testing that is used to explore particle failures and fission product release from compacts. Two systems were installed in the Irradiated Fuels Examination Facility (IFEL) at Oak Ridge National Laboratory (ORNL). The targeted design […]