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 […]
Data Compilation for AGR-2 B&W UO₂ Compact Lot LEU11-OP2-Z (Revision 1)
This document is a compilation of characterization data for the candidate AGR-2 B&W UO2 fuel compact lot LEU11-OP2-Z. The compacts were produced by ORNL for the Advanced Gas Reactor Fuel Development and Qualification (AGR) program for the second AGR irradiation test (AGR-2). This compact lot was fabricated using particle composite LEU11. LEU11 came from Babcock and […]
Data Compilation for AGR-2 UCO Variant Compact Lot LEU09-OP2-Z
This document is a compilation of characterization data for the candidate AGR-2 UCO Variant fuel compact lot LEU09-OP2-Z. The compacts were produced by ORNL for the Advanced Gas Reactor Fuel Development and Qualification (AGR) program for the second AGR irradiation test (AGR-2). This compact lot was fabricated using particle composite LEU09. LEU09 came from Babcock […]
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 […]
Data Compilation for AGR-2 Variant Coated Particle Batch G73J-14-93073A
Coated particle fuel batch G73J-14-93073A was produced by the Babcock and Wilcox Company (B&W) for possible selection as UCO variant fuel for the Advanced Gas Reactor Fuel Development and Qualification Program’s AGR-2 irradiation test. Batch G73J-14-93073A is a single batch of TRISO-coated 425 μm nominal diameter 14% low enrichment uranium oxide/uranium carbide kernels (LEUCO). The […]
Ceramography of Irradiated tristructural isotropic (TRISO) Fuel from the AGR-2 Experiment
Ceramography was performed on cross sections from four tristructural isotropic (TRISO) coated particle fuel compacts taken from the AGR-2 experiment, which was irradiated between June 2010 and October 2013 in the Advanced Test Reactor (ATR). The fuel compacts examined in this study contained TRISO-coated particles with either uranium oxide (UO2) kernels or uranium oxide/uranium carbide […]
AGR-2 Irradiated Test Train Preliminary Inspection and Disassembly First Look
The AGR 2 irradiation experiment began in June 2010 and was completed in October 2013. The test train was shipped to the Materials and Fuels Complex in July 2014 for post-irradiation examination (PIE). The first PIE activities included nondestructive examination of the test train, followed by disassembly of the test train and individual capsules and […]
AGR-2 Irradiation Test Final As-Run Report (Revision 4)
This document presents the as run analysis of the AGR 2 irradiation experiment. AGR 2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technology […]
Uncertainty Quantification of Calculated Temperatures for the U.S. Capsules in the AGR-2 Experiment
A series of Advanced Gas Reactor (AGR) irradiation experiments are being conducted within the Advanced Reactor Technology (ART) Fuel Development and Qualification Program. The main objectives of the fuel experimental campaign are to provide the necessary data on fuel performance to support fuel process development, qualify a fuel design and fabrication process for normal operation […]
Release-to-Birth Ratios for AGR-2 Operating Cycles 147A through 154B
This Engineering Calculations and Analysis Report (ECAR) documents the release-to-birth (R/B) ratios of the Advanced Gas Reactor (AGR) experiment, AGR-2, irradiated in the Advanced Test Reactor (ATR) B-12 position during Cycle 147A (AGR-2 irradiation interval #1) through Cycle 154B (AGR-2 irradiation interval #11).