AGR-2 Irradiation Test Final As-Run Report, Rev 2
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) Technical Development Office (TDO) […]
AGR-2 Final Data Qualification Report for U.S. Capsules – ATR Cycles 147A Through 154B
This report provides the data qualification status of AGR-2 fuel irradiation experimental data in four U.S. capsules from all 15 Advanced Test Reactor (ATR) Cycles 147A, 148A, 148B, 149A, 149B, 150A, 150B, 151A, 151B, 152A, 152B, 153A, 153B, 154A, and 154B, as recorded in the Nuclear Data Management and Analysis System (NDMAS). Thus, this report […]
AGR-1 Post-Irradiation Examination Test Requirements
As the first in a series of test irradiations for the NGNP Fuel Development and Qualification Program, the AGR-1 Irradiation Experiment is scheduled to begin irradiation in the Advanced Test Reactor in December 2006. At the conclusion of the experiment, the test train will be removed from the reactor and shipped to the Hot Fuel […]
AGR-1 Post Irradiation Examination Final Report
The post-irradiation examination (PIE) of the Advanced Gas Reactor (AGR)-1 experiment was a multi-year, collaborative effort between Idaho National Laboratory (INL) and Oak Ridge National Laboratory (ORNL) to study the performance of UCO (uranium carbide, uranium oxide) tristructural isotropic (TRISO) coated particle fuel fabricated in the U.S. and irradiated at the Advanced Test Reactor at […]
AGR-1 Irradiated Test Train Preliminary Inspection and Disassembly First Look
The AGR-1 irradiation experiment ended on November 6, 2009, after 620 effective full power days in the Advanced Test Reactor, achieving a peak burnup of 19.6% FIMA. The test train was shipped to the Materials and Fuels Complex in March 2010 for post-irradiation examination. The first PIE activities included non-destructive examination of the test train, […]
Ceramographic Examinations of Irradiated AGR-1 Fuel Compacts
The AGR-1 experiment involved irradiating 72 cylindrical fuel compacts containing tri-structural isotropic (TRISO)-coated particles to a peak burnup of 19.5% fissions per initial metal atom with no in-pile failures observed out of almost 300,000 particles. Six irradiated AGR 1 fuel compacts were selected for microscopy that span a range of irradiation conditions (temperature, burnup, and […]
Analysis of Fission Products on the AGR-1 Capsule Components
The components of the AGR-1 irradiation capsules were analyzed to determine the retained inventory of fission products in order to determine the extent of in-pile fission product release from the fuel compacts. This includes analysis of (1) the metal capsule components, (2) the graphite fuel holders, (3) the graphite spacers, and (4) the gas exit […]
Data Compilation for AGR-1 Variant 3 Compact Lot LEU01-49T-Z
This document is a compilation of characterization data for the AGR-1 vriant 3 fuel compact lot LEU01-49T-Z. The compacts were produced by ORNL for the Advanced Gas Reactor Fuel Development and Qualification (AGR) program for the first AGR irradiation test train (AGR-1). This compact lot was fabricated using particle composite LEU01-49T, which was a composite […]
Data Compilation for AGR-1 Variant 2 Compact Lot LEU01-48T-Z
This document is a compilation of characterization data for the AGR-1 variant 2 compact lot LEU01-48T-Z. The compacts were produced by ORNL for the Advanced Gas Reactor Fuel Development and Qualification (AGR) program for the first AGR irradiation test train (AGR-1). This compact lot was fabricated using particle composite LEU01-48T, which was a composite of […]
Data Compilation for AGR-1 Variant 1 Compact Lot LEU01-47T-Z
This document is a compilation of characterization data for the AGR-1 variant 1 compact lot LEU01-47T-Z. The compacts were produced by ORNL for the ADvanced Gas Reactor Fuel Development and Qualification (AGR) program for the first AGR irradiation test train (AGR-1). This compact lot was fabricated using particle composite LEU01-47T, which was a composite of […]