Ian C Gauld Distinguished R&D Staff Contact gauldic@ornl.gov | 865.574.5257 All Publications Analysis of PNAR Spent Fuel Safeguards Measurements using the ORIGEN Data Analysis Module... Analysis with the ORIGEN Module of PNAR Spent Fuel Measurements for Nuclear Safeguards Applications Status Update on the High Precision Isotopic Measurements on High Burnup LWR Fuel in 2020 SFCOMPO Database of Spent Nuclear Fuel Assay Data – the Next Frontier Validation of ORIGEN for VVER-440 Spent Fuel with Application to Fork Detector Safeguards Measurements Nuclear Data – Benchmarking 19F(alpha,n) Yield Data for Nuclear Safeguards... Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory (α,n) reactions in oxide compounds calculated from the R-matrix theory... Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit... 17,18 O(a,n) Evaluated Cross Sections to Improve National Security Applications... Prioritizing Nuclear Data Needs Using Uncertainty Analysis... Advancing the Fork detector for quantitative spent nuclear fuel verification Advancing the Fork detector for quantitative spent nuclear fuel verification... Integral nuclear data validation using experimental spent nuclear fuel compositions... Early applications of the R -matrix SAMMY code for charged-particle induced reactions and related covariances... SFCOMPO-2.0: An OECD NEA Database of Spent Nuclear Fuel Isotopic Assays, Reactor Design Specifications, and Operating Data... Analysis of New Measurements of Isotopic Compositions in Spent Fuel Samples from Calvert Cliffs Unit 1 Reactor using SCALE 6.... Integral Nuclear Data Validation Using Experimental Spent Nuclear Fuel Compositions... In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification Validation of ORIGEN-S Decay Heat Predictions for LOCA Analysis Analysis of new measurements of Calvert Cliffs spent fuel samples using SCALE 6.2 Systematic Approach to Nuclear Data Uncertainty Quantification for Nuclear Security Applications... High-Fidelity Modeling of Spent Fuel Assemblies for Advanced NDA Instrument Testings... Uncertainty Quantification in (α,n) Neutron Source Calculations for an Oxide Matrix... Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links ORCID
