​​​​Reports - Fuel Qualification​

  
  
  
Description
  
  
AGR-5/6/7 Irradiation Test Final As-Run ReportFuel 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-5/6/7Fuel 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 ATRFuel 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 168AFuel 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 ExperimentsFuel 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)-AFuel 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 ExperimentFuel 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 10-4Fuel 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 ProgressFuel 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 ExperimentFuel 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 PlanFuel 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 DescriptFuel 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 3-1-1Fuel 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.pdfFuel 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 ReportFuel 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