Explanipedia

Sister Rod Destructive Examinations (FY23): Appendix J: Leaching of High Burnup Used Nuclear Fuel in Deionized Water Open

Yadukrishnan Sasikumar, William J. Nuttall, Tamara Keever, Darren Skitt, Rose Montgomery , et al. · 2024

The leaching experiment aims to understand the trends in the radiolysis-enhanced dissolution of HBU SNF when exposed to water (e.g., in-reactor or in-pool cladding failures). Specimens from a baseline M5-clad rod and a heat-treated M5 rod …

Sister Rod Destructive Examinations (FY23) Appendix E2: Four-Point Bend Fractured Specimen Images Open

Rose Montgomery, Darren Skitt · 2024

This appendix provides images of the segments broken in four-point bending (4PB) as a part of the Sister Rod project.

Post-irradiation examination and safety testing of US AGR-2 irradiation test compacts Open

John Hunn, Robert Morris, Fred Montgomery, Tyler Gerczak, Darren Skitt , et al. · 2023

Multi-scale Analysis of Failed Safety Tested UO2 Particles from the AGR-2 Fuel Irradiation Experiment Open

Tyler Gerczak, John Hunn, Grant Helmreich, Fred Montgomery, Robert Morris , et al. · 2023

Long-term thermal testing of irradiated TRISO fuel particles from the AGR-2 experiment Open

Tyler Gerczak, John Hunn, Zachary Burns, Darren Skitt · 2023

Determination of Average Burnup in AGR-3/4 Compacts 1-4 and 7-4 Open

Grant Helmreich, John Hunn, Fred Montgomery, Darren Skitt, Tamara Keever , et al. · 2023

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 Reacto…

Comparison of unirradiated and irradiated AGR-2 TRISO fuel particle oxidation response Open

Darren Skitt, Rachel Seibert, Tyler Gerczak, Grant Helmreich, Zachary Burns , et al. · 2023

Microstructure of irradiated AGR TRISO particle buffer layers as measured by X-ray computed tomography Open

Grant Helmreich, Andrew K. Kercher, Tyler Gerczak, Dylan Richardson, Fred Montgomery , et al. · 2022

Safety Testing of AGR-5/6/7 Compacts 2-2-2 and 2-2-4 Open

John Hunn, Will Cureton, Darren Skitt, Fred Montgomery · 2022

Compacts 2-2-2 and 2-2-4 from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program’s final irradiation campaign (AGR-5/6/7) were each separately subjected to a thermal soak at 1600°C for 300 h under flowing helium to s…

Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compacts 1-3, 4-3, 10-1, and 10-2 Open

Grant Helmreich, John Hunn, Fred Montgomery, Darren Skitt · 2022

The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program’s third and fourth irradiation experiments (AGR-3/4), originally planned as separate tests, were combined into one test train for irradiation in the Advanced Test Re…

Sister Rod Destructive Examinations (FY2021) Appendix E Mechanical Testing Open

Rose Montgomery, Darren Skitt, Muhammet Ayanoglu, Yong Yan, Ben Garrison · 2022

As a part of the DOE NE High Burnup Spent Fuel Data Project, Oak Ridge National Laboratory (ORNL) is performing destructive examinations (DEs) of high burnup (HBU) (>45 GWd/MTU) spent nuclear fuel (SNF) rods from the North Anna Nuclear Pow…

Sister Rod Destructive Examinations (FY2021) Appendix H: Instron Uncertainty Calculations Open

Darren Skitt, Rose Montgomery · 2022

This report provides estimates of the experimental uncertainties associated with mechanical tests performed on high burnup fuel rod segments.

Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4 Open

John Hunn, Fred Montgomery, Darren Skitt, Grant Helmreich · 2020

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 Reacto…

AGR-2 Loose Particle Heating Tests in the Furnace for Irradiated TRISO Testing Open

Tyler Gerczak, John Hunn, Robert Morris, Darren Skitt, Zachary Burns · 2020

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 fissio…

Summary of the Postirradiation Examination of the First Samples from a MiniFuel Irradiation Open

Jason Harp, Robert Morris, Christian Petrie, Joseph R. Burns, Darren Skitt , et al. · 2020

An overview of postirradiation examination results for uranium nitride kernels and uranium nitride coated particles irradiated in the High Flux Isotope Reactor are presented. This is the first postirradiation examination of the MiniFuel ir…

Analysis of fission product distribution and composition in the TRISO layers of AGR-2 fuel Open

Tyler Gerczak, John Hunn, Robert Morris, Fred Montgomery, Darren Skitt , et al. · 2020

Safety Testing and Destructive Examination of AGR-2 UO<sub>2</sub> Compact 3-1-1 Open

John Hunn, Robert Morris, Fred Montgomery, Darren Skitt, Zachary Burns · 2020

Post-irradiation examination and elevated-temperature safety testing are being performed on compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program’s second irradiation experiment (AGR-2). The compacts in th…

Acceptance Test Data for BWXT Coated Particle Batches 93172B and 93173B—Defective IPyC and Pyrocarbon Anisotropy Open

John Hunn, Grant Helmreich, John Dyer, Austin Schumacher, Darren Skitt · 2017

Coated particle batches J52O-16-93172B and J52O-16-93173B were produced by Babcock and Wilcox Technologies (BWXT) as part of the production campaign for the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program’s AGR-5/6/7 …

X-ray Analysis of Defects and Anomalies in AGR-5/6/7 TRISO Particles Open

Grant Helmreich, John Hunn, Darren Skitt, John Dyer, Austin Schumacher · 2017

Coated particle fuel batches J52O-16-93164, 93165, 93166, 93168, 93169, 93170, and 93172 were produced by Babcock and Wilcox Technologies (BWXT) for possible selection as fuel for the Advanced Gas Reactor Fuel Development and Qualification…

Acceptance Test Data for the AGR-5/6/7 Irradiation Test Fuel Composite Defective IPyC Fraction and Pyrocarbon Anisotropy Open

Grant Helmreich, John Hunn, Darren Skitt, John Dyer, Austin Schumacher · 2017

Coated particle composite J52R-16-98005 was produced by Babcock and Wilcox Technologies (BWXT) as fuel for the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program’s AGR-5/6/7 irradiation test in the Idaho National Laborat…

Acceptance Test Data for Candidate AGR-5/6/7 TRISO Particle Batches BWXT Coater Batches 93165 93172 Defective IPyC Fraction and Pyrocarbon Anisotropy Open

Grant Helmreich, John Hunn, Darren Skitt, John Dyer, Austin Schumacher · 2017

Coated particle fuel batches J52O-16-93165, 93166, 93168, 93169, 93170, and 93172 were produced by Babcock and Wilcox Technologies (BWXT) for possible selection as fuel for the Advanced Gas Reactor Fuel Development and Qualification (AGR) …

Acceptance Test Data for BWXT Coated Particle Batch 93164A Defective IPyC Fraction and Pyrocarbon Anisotropy Open

Grant Helmreich, John Hunn, Darren Skitt, John Dyer · 2017

Coated particle fuel batch J52O-16-93164 was produced by Babcock and Wilcox Technologies (BWXT) for possible selection as fuel for the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program’s AGR-5/6/7 irradiation test in th…

UN TRISO Compaction in SiC for FCM Fuel Irradiations Open

Kurt A. Terrani, Michael Trammell, Jim Kiggans, Brian Jolly, Darren Skitt · 2016

The U.S. Department of Energy Office of Nuclear Energy (DOE-NE) Advanced Fuels Campaign (AFC) is conducting research and development to elevate the technology readiness level of Fully Ceramic Microencapsulated (FCM) fuels, a candidate nucl…

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