Publications

Nov, 2023

Journal

Failure analysis of nuclear transient-tested UN tristructural isotropic fuel particles in a 3D printed SiC matrix

Fully ceramic microencapsulated fuel elements containing UN tristructural isotropic (TRISO) fuel particles within a 3D printed SiC matrix were subjected to transient testing with varying energy depositions. Detailed post-irradiation examinations were performed, including leaching in hot HNO3 and post-leaching X-ray computed tomography, to quantify the percentage of failed…

Nov, 2023

ORNL Report

Analysis of Epic Shadow 23-01 Specimens for the National Nuclear Materials Archive: Exemplar Records 38-TYP-26 and 38-TYP-28

Nov, 2023

ORNL Report

Analysis of Specimens for the National Nuclear Materials Archive: Exemplar Record 11-TYP-65-1

Nov, 2023

ORNL Report

Sister Rod Destructive Examinations (FY22) Appendix I: SNF Aerosols Released During Rod Fracture

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 Power Station operated by Dominion Energy. The SNF rods, called sister rods or sibling rods, are all HBU and include four different kinds o…

Nov, 2023

ORNL Report

Sister Rod Destructive Examinations (FY21) Appendix C: Rod Internal Pressure, Void Volume, and Gas Transmission Tests

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 Power Station operated by Dominion Energy [C-1]. The SNF rods, called the sister rods or sibling rods, are all HBU and include four differe…

Nov, 2023

ORNL Report

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

Nov, 2023

ORNL Report

Analysis of Skull Oxide for the National Nuclear Materials Archive: Exemplar Record 36-TYP-55

Nov, 2023

ORNL Report

Analysis of Tablet for the National Nuclear Materials Archive: Exemplar Record UC37-FZG-01

May, 2016

Journal

Reactor Production of Thoruim-229

Limited availability of 229Th for clinical applications of 213Bi necessitates investigation of alternative production routes. In reactor production, 229Th is produced from neutron transmutation of 226Ra, 228Ra, 227Ac and 228Th. We evaluate irradiations of 226Ra, 228Ra, and 227Ac targets at the ORNL High Flux Isotope Reactor. Yields of 229Th at 25 days are 2.0 ± 0.2 mCi/g,…

Oct, 2015

Journal

Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation

Mar, 2014

Conference Paper

ADAPTATION OF HPLC-ICPMS MEASUREMENT PROTOCOLS FOR NUCLEAR PROJECTS AT THE OAK RIDGE NATIONAL LABORATORY

Mar, 2011

Conference Paper

Detailed Destructive Post-Irradiation Examinations of Mixed Uranium and Plutonium Oxide Fuel