| | Kernel Buffer Volume Fraction Margin of the AGR Designed Fuel Particle | Fuel Qualification | Modeling results used to assess the fuel performance of the TRISO-coated fuel particles as a function of kernel/buffer volume fraction include SiC tangential stress, formation of the buffer/IPyC gap, particle temperature profile, internal particle pressure, fission gas released from the kernel, probability of fuel particle failure, and fission product diffusion. | 3/15/2023 |
| | AGR-5/6/7 Irradiation Test Final As-Run Report | Fuel Qualification | This document presents the as-run analysis of the AGR-5/6/7 irradiation experiment. AGR-5/6/7 is the last of a series of experiments conducted in the ATR at INL in support of the development and qualification of tri-structural isotropic low-enriched fuel for use in high-temperature gas-cooled reactors. | 9/7/2021 |
| | Automated Internal Energy Calibration by OnTheFly for AGR-5/6/7 | Fuel Qualification | The software program, OnTheFly, was developed at INL to keep HPGe detectors energy calibrated during very long experiments. Over time, spectra produced from a HPGe detector will slowly stretch or contract, causing the energy calibration to change. If the energy calibration changes too much, it will cause energy lines to be misidentified. | 5/14/2021 |
| | As-Run Thermal Analysis for the AGC-4 Experiment Irradiated in the ATR | Fuel Qualification | The Advanced Graphite Capsule (AGC) irradiation experiment will provide irradiation creep rate data for the new graphite proposed for the Next Generation Nuclear Plant (NGNP) program. The fourth experiment in the series (AGC-4) was designed to irradiate various types of graphite specimens at a temperature of 900 ºC and targeted displacements per atom (DPA) of 6. | 4/27/2021 |
| | AGR-5/6/7 Data Qualification Report for ATR Cycles 162B through 168A | Fuel Qualification | This report provides the qualification status of experimental data for the AGR-5/6/7 fuel irradiation. AGR-5/6/7 was conducted in the ATR at INL in support of the development and qualification of TRISO low-enriched fuel for use in high-temperature gas-cooled reactors. | 4/21/2021 |
| | Advanced Microscopy Report on UCO Fuel Kernels from Selected AGR-1 and AGR-2 Experiments | Fuel Qualification | A variety of neutron irradiation experiments were completed at INL on TRISO coated particles contained in a graphitic matrix as part of the Advanced Gas Reactor (AGR) fuel development and qualification program. Although the initially advanced microscopy and microanalysis studies on AGR-1 particles focused predominantly on the SiC layer's role as the main fission-product containment, studies were further expanded to evaluate UCO kernels of selected AGR-1 and AGR-2 coated particles. | 3/29/2021 |
| | UCO TRISO-Coated Particle Fuel Performance—Topical Report EPRI-AR-1(NP)-A | Fuel Qualification | Uranium Oxycarbide (UCO) Tristructural Isotropic (TRISO)-Coated Particle Fuel Performance—Topical Report EPRI-AR-1(NP)-A | 11/20/2020 |
| | Comparison between PARFUME and Bison Using the AGR-2 Irradiation Experiment | Fuel Qualification | This report documents comparisons between Fuel Model (PARFUME) model predictions versus Bison for selected compacts from the second irradiation test of the Advanced Gas Reactor (AGR) program that occurred from June 2010 to October 2013 in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). PARFUME is a fuel performance analysis and modeling code, used for evaluating gas-reactor tristructural isotropic (TRISO) coated particle fuel for prismatic, pebble bed, plate, and cylindrical type fuel geometries. | 9/24/2020 |
| | Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4 | Fuel Qualification | The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program third and fourth irradiation experiments (AGR-3/4), originally planned as separate tests, were combined in one test train for irradiation in the Advanced Test Reactor at Idaho National Laboratory (INL). | 9/1/2020 |
| | AGR-5/6/7 Experiment Monitoring and Simulation Progress | Fuel Qualification | Advanced Gas Reactor (AGR)--5/6/7 is the last of a series of AGR experiments conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) in support of development and qualification of tri-structural isotropic (TRISO) low-enriched fuel for use in high temperature gas-cooled reactors. The test train contains five separate capsules that are independently controlled and monitored. Each capsule contains multiple 12.51 mm long compacts filled with low-enriched uranium carbide/oxide (UCO) TRISO fuel particles. | 8/26/2020 |
| | Comparison of Fission Product Release Predictions using PARFUME with Results from the AGR-2 Irradiation Experiment | Fuel Qualification | The PARFUME (PARticle FUel ModEl) code was used to predict fission product release from tristructural isotropic (TRISO) coated fuel particles and compacts during the second irradiation experiment (AGR-2) of the Advanced Gas Reactor Fuel Development and Qualification Program. | 8/14/2020 |
| | AGR-5/6/7 Post-Irradiation Examination Plan | Fuel Qualification | This plan describes the PIE activities to be carried out on AGR-5/6/7 fuel and the non-fuel components of the AGR-5/6/7 irradiation test train. PIE of AGR-5/6/7 fuel and test train components will provide data on fuel performance over a range of irradiation conditions (e.g., burnup, neutron fluence, and temperature), test fuel under postulated accident conditions, and support development of fuel performance and fission product transport models. | 8/11/2020 |
| | NDMAS System and Process Descript | Fuel Qualification | The DOE has made a significant investment in research to develop the next generation of reactor technologies as well as to improve the performance and lengthen the life cycle of existing nuclear reactors. Data collected to demonstrate new concepts may also be used in the future to support licensing of these technologies. Provenance of these data must be preserved. The NDMAS was established to manage and preserve data collected by fuels and materials research conducted by the high-temperature, gas-cooled reactor program. | 4/16/2020 |
| | Safety Testing and Destructive Examination of AGR-2 UO2 Compact 3-1-1 | Fuel Qualification | Post-irradiation examination and elevated-temperature safety testing are being performed on compacts from the Advanced Gas Reactor Fuel Development and Qualification Program’s AGR-2. The compacts in the AGR-2 irradiation experiment held either tristructural isotropic (TRISO)-coated particles containing uranium oxide fuel kernels or TRISO-coated particles containing fuel kernels with both uranium carbide and uranium oxide phases. | 2/1/2020 |
| | https://art.inl.gov/ReportsFolder/MaterialPropertiesReport.pdf | Fuel Qualification | The purpose of this study is to identify the material properties that have the largest impact on the failure probability of TRISO-coated fuel particles under irradiation. The TRISO fuel performance modeling code PARFUME was used to assess the material properties that have the main influence on the probability of failure of the silicon carbide (SiC) layer of TRISO fuel particles. | 8/1/2018 |
| | AGR-2 Irradiation Test Final As-Run Report | Fuel Qualification | The objectives of the AGR 2 experiment are to: 1) Irradiate UCO and UO2 fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR 1 test and other project activities. 2) Provide irradiated fuel samples for PIE and safety testing. 3) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. | 2/1/2018 |
