Brad Rearden Contact 865.341.4663 | REARDENBT@ORNL.GOV All Publications Fiscal Year 2016 Report on SCALE Maintenance and Development (ORNL/SR-2017/152) Diagnosing Undersampling Biases in Monte Carlo Eigenvalue and Flux Tally Estimates SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations Development of a Generalized Perturbation Theory Method for Uncertainty and Sensitivity Analysis using Continuous-Energy Monte Carlo Methods Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization Monte Carlo Capabilities of the SCALE Code System Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA Determination and Application of Partial Biases in Criticality Safety Validation Criticality Safety Validation of SCALE 6.1 Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE Monte Carlo Criticality Methods and Analysis Capabilities in SCALE Application of the SCALE TSUNAMI Tools for the Validation of Criticality Safety Calculations Involving <sup>233</sup>U (ORNL/TM-2008/196) SCALE-6 Sensitivity/Uncertainty Methods and Covariance Data Recent Use of Covariance Data for Criticality Safety Assessment Use of Sensitivity and Uncertainty Analysis in the Design of Reactor Physics and Criticality Benchmark Experiments for Advanced Nuclear Fuel Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques Perturbation Theory Eigenvalue Sensitivity Analysis with Monte Carlo Techniques Key Links Curriculum Vitae
