Travis M Greene Nuclear Criticality Safety - Research and Development Associate Contact 865.574.7823 | GREENETM@ORNL.GOV All Publications Porosity in nuclear graphite and its impact on nuclear reactor science and criticality safety applications Verified, Archived Library of Inputs and Data (VALID) Online Repository... Design of Critical Experiments Involving Graphite elements at the IPEN/MB-01 Plate-Type Core R-matrix analysis of n+natCl reactions up to 1.2 MeV SCALE Developments for the U.S. Nuclear Criticality Safety Program: Recent Achievements and Outlook Investigating Hydrogen Thermal Scattering Law Data with Critical Benchmarks Calculation of Extended Subcritical Mass Limits in ANSI/ANS-8.1-2014... Investigating Similarity Differences for Light-Water-Moderated and Polyethylene-Moderated Systems DETERMINISTIC-MONTE CARLO HYBRID METHODS FOR EIGENVALUE SENSITIVITY COEFFICIENT CALCULATIONS Conducting MUSiC Modeling Studies Validating Mixtures of 233U, 235U, and 239Pu for the Sum-of-Fractions Method Impact of Increased Monte Carlo Parameters on Sensitivity Calculations with SCALE... Investigating a Potential Hafnium Bias in SCALE Procedure for the Computational Models created for the DOE/NRC Collaboration for Criticality Safety Support for Commercial-Scale HALEU Fuel Cycles Project (DNCSH) 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 Performance of the Initial Implementation of the Shift Monte Carlo Code in SCALE 6.3 Applicability of ORCEF UF4/CF2 Experiments to Validation of 30-Inch UF6 Cylinders Expansion of the ORNL VALID Library 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 Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Applications, Methods, and Data Section Criticality Safety Analysis & Research Group SCALE
