Shane W Hart Postdoctoral Research Associate Contact hartsw@ornl.gov | 865.241.9709 All Publications Comparison of Temperature-Dependent Cross Section Treatments Within the Shift Monte Carlo Radiation Transport Code SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems Improvement of SCALE Infrastructure on Microsoft Windows Proposed Subcritical Assembly for Nuclear Criticality Safety Training at the Oak Ridge National Laboratory A Subcritical Assembly for Training and Education Use at the Oak Ridge National Laboratory... Creation of the VADER Code in SCALE Modernization of ORIGEN Library Creation in the SCALE Computer Code VADER: A Tool for Criticality Safety Validation Feasibility Study for a Proposed Subcritical Assembly at Oak Ridge National Laboratory Secondary-Source Core Reload Modeling with VERA Estimation of External Contamination and Exposure Rates Due to Fission Product Release Molten Salt Reactor Fuel Depletion Tools in SCALE Source Range Detector Response Modeling using VERA Sub-libraries In Origen Warthog: At the Intersection of MOOSE and SHARP... Implementation of the Direct S(A,B) method in the KENO Monte Carlo code... Implementation of the Direct S(A,B) method in the KENO Monte Carlo code Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code... Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code CRITICALITY SAFETY ENHANCEMENTS FOR SCALE 6.2 AND BEYOND... Monte Carlo Capabilities of the SCALE Code System Key Links ORCID 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
