Travis Greene Contact GREENETM@ORNL.GOV All Publications R-matrix analysis of n+natCl reactions up to 1.2 MeV Investigating Hydrogen Thermal Scattering Law Data with Critical Benchmarks Calculation of Extended Subcritical Mass Limits in ANSI/ANS-8.1-2014... Conducting MUSiC Modeling Studies Validating Mixtures of 233U, 235U, and 239Pu for the Sum-of-Fractions Method Investigating Similarity Differences for Light-Water-Moderated and Polyethylene-Moderated Systems DETERMINISTIC-MONTE CARLO HYBRID METHODS FOR EIGENVALUE SENSITIVITY COEFFICIENT CALCULATIONS Impact of Increased Monte Carlo Parameters on Sensitivity Calculations with SCALE... Investigating a Potential Hafnium Bias in SCALE The Case for and Against a Gadolinium Bias in SCALE: Round 2 Impact of Thermal Scattering Law on Similarity Assessment in Light-water or Polyethylene-Moderated Systems Applicability of ORCEF UF4/CF2 Experiments to Validation of 30-Inch UF6 Cylinders Expansion of the ORNL VALID Library Performance of the Initial Implementation of the Shift Monte Carlo Code in SCALE 6.3 Impact of Increased Latent Generations on Sensitivity Calculations with SCALE... Revision to SCALE Procedure for Verified, Archived Library of Inputs and Data (VALID) Expanded Validation of Uranium Systems with the KENO Monte Carlo Codes and SCALE 6.2.4... Cumulative χ2 Metric for VALID for ENDF/B-VII.1 and ENDF/B-VIII.0 in SCALE 6.3b9... Reducing Direct Perturbation Uncertainty for High-Sensitivity Coefficients Verification of Subcritical Limits in ANSI/ANS-8.1-2014 Nuclear Data and Cross Section Testing Using ENDF/B-VIII.0 SCALE 6.2.4 Validation: Nuclear Criticality Safety Description and Use of SCALE Sampler Parametric Capability for Engineering Analysis and Optimization Verification of Subcritical Limits in ANSI/ANS-8.1-2014... VALIDATION OF KENO V.A AND KENO-VI IN SCALE 6.3 BETA 3 USING ENDF/B-VII.1 AND ENDF/B-VIII LIBRARIES Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Data, Criticality Safety, and Radiation Transport Section Nuclear Criticality Safety Group SCALE
