Steve E Skutnik R&D Staff, Nuclear Reactor Analyst Contact 515.231.3547 | skutnikse@ornl.gov All Publications Survey of prospective techniques for molten salt reactor feed monitoring High Flux Isotope Reactor Neutron Spectrum Shape Estimation From Activation Experiment Data Assessment of ORIGEN Reactor Library Development for Pebble-Bed Reactors Based on the PBMR-400 Benchmark Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr Designing a Molten Salt Reactor Feed Monitoring System... SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs Modeling and Simulation of Xe-100 type Pebble Bed Gas-Cooled Reactor with SCALE Transition Core Modeling for Extended Enrichment & Accident Tolerant Fuels Using Polaris/PARCS Uncertainty Quantification of Pebble's Discharge Burnup and Isotopic Inventory using SCALE Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor... SCALE Modeling of the Fast Spectrum Heat Pipe Reactor Rapid Depletion Analysis of Flowing-Pebble Reactor Systems at Equilibrium using SCALE Overview of Recent SCALE Activities for Non-LWR Inventory and Decay Heat Analysis Initial Development of a Generic Fluoride Salt-Cooled Reactor Model SOURCE TERM AND DEPLETION COUPLING WITH DYNAMIC SYSTEM MODELING SOLUTIONS FOR FUEL CYCLE OPERATIONS Modeling of the Molten Salt Reactor Experiment with SCALE Thermal Hydraulic Modeling of the Kairos Power Generic Fluoride High Temperature Reactor in MELCOR (alpha,n) nuclear data scoping study... Relevant Advanced Reactor Benchmarks for Nuclear Data Assessment Nuclear Data Scoping Studies for Nonproliferation - paper Sensitivity Analysis for Best-Estimate Thermal Models of Vertical Dry Cask Storage Systems A GENERALIZED METHOD FOR CHARACTERIZATION OF 235U AND 239PU CONTENT USING SHORT-LIVED FISSION PRODUCT GAMMA SPECTROSCOPY... A GENERALIZED METHOD FOR FISSILE MASS CHARACTERIZATION USING SHORT-LIVED FISSION PRODUCT GAMMA MEASUREMENTS... Creating NDA “working standards” through high-fidelity spent fuel modeling... Key Links Google Scholar ORCID GitHub Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Modeling and Simulation Development and Deployment Section Nuclear Code Integration Group SCALE
