Brad Rearden Contact REARDENBT@ORNL.GOV All Publications Fiscal Year 2016 Report on SCALE Maintenance and Development (ORNL/SR-2017/152) Development of a Generalized Perturbation Theory Method for Uncertainty and Sensitivity Analysis using Continuous-Energy Monte Carlo Methods Diagnosing Undersampling Biases in Monte Carlo Eigenvalue and Flux Tally Estimates SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations Monte Carlo Capabilities of the SCALE Code System 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 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 Monte Carlo Criticality Methods and Analysis Capabilities in SCALE Criticality Safety Validation of SCALE 6.1 Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE Application of the SCALE TSUNAMI Tools for the Validation of Criticality Safety Calculations Involving <sup>233</sup>U (ORNL/TM-2008/196) Recent Use of Covariance Data for Criticality Safety Assessment SCALE-6 Sensitivity/Uncertainty Methods and Covariance Data 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 ORCID
