Alex Lang Nuclear Criticality Safety Engineer Contact LANGA@ORNL.GOV All Publications Bias and Bias Uncertainty for High Burnup and Extended Enrichment Fuels in Criticality Safety Analyses Validation Studies Burnup Credit Loading Curves for High-Burnup and Extended Enrichment Fuels Credible Criticality Safety Margin in the 30B Package with LEU+ UF6 and Hypothetical Water Ingress Validating Mixtures of 233U, 235U, and 239Pu for the Sum-of-Fractions Method USE OF SCALE MAVRIC RADIATION TRANSPORT CALCULATIONS FOR THE DESIGN OF A SUBCRITICAL ASSEMBLY AT OAK RIDGE NATIONAL LABORATORY Effect of Decay Time on Criticality Safety Analyses for High Burnup and Extended Enrichment Fuels ASSESSMENT OF VALIDATION FOR BURNUP CREDIT CALCULATIONS FOR LEU+ AND HIGH BURNUP FUEL Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels IMPACT OF RECENT ENDF NUCLEAR DATA ON BURNUP CREDIT CRITICALITY SAFETY ANALYSES BASIS OF 10CFR71.15(B) FOR CONSIDERATION INTO SSR-6 PARA. 417 ASSESSMENT OF EXISTING TRANSPORTATION PACKAGES FOR USE WITH LEU+ AND HALEU MATERIAL BASIS FOR FISSILE EXEMPTION 10CFR71.15(B) Impact of Thermal Scattering Law on Similarity Assessment in Light-water or Polyethylene-Moderated Systems Proposed Subcritical Assembly for Nuclear Criticality Safety Training at the Oak Ridge National Laboratory Current Progress of the Final Design of a Subcritical Assembly at the Oak Ridge National Laboratory... DOE-EM NCS Needs Program History and Current Efforts Expansion of the ORNL VALID Library Recent Assessments of Existing Transportation Packages for Use with HALEU Material Multigroup Examination of Nickel-Reflected HEU System A Subcritical Assembly for Training and Education Use at the Oak Ridge National Laboratory Post-closure Nuclear Criticality Safety Evaluations for Disposition of Criticality Control Overpacks at the Waste Isolation Pilot Plant Discovery of AMPX Thermal Scattering Law Processing Issue for Solid Moderators Sensitivity Calculations for Systems with Polyethylene Reflector Materials Using CLUTCH Analysis of the 30B UF6 Container for Use with Increased Enrichment... 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
