Alex

Alex Lang

Nuclear Criticality Safety Engineer

Contact

865.341.1915 | LANGA@ORNL.GOV

All Publications

Impact of recent ENDF nuclear data update, high initial enrichment and high burnup fuel on critical experiments applicability determination via the integral index ck for burnup credit validation
Final CRADA Report: NFE-23-09571 Criticality Safety Analysis for NuCycle
Perturbations to the 30B-10 Cylinder Criticality Control System
Improving Transport Efficiency of HALEU Fuel with a Modified Criticality Control System in the 30B-10
Burnup Credit Loading Curves for High-Burnup and Extended Enrichment Fuels
Bias and Bias Uncertainty for High Burnup and Extended Enrichment Fuels in Criticality Safety Analyses Validation Studies
Credible Criticality Safety Margin in the 30B Package with LEU+ UF6 and Hypothetical Water Ingress
ASSESSMENT OF VALIDATION FOR BURNUP CREDIT CALCULATIONS FOR LEU+ AND HIGH BURNUP FUEL
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
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
A Subcritical Assembly for Training and Education Use at the Oak Ridge National Laboratory
Multigroup Examination of Nickel-Reflected HEU System
Post-closure Nuclear Criticality Safety Evaluations for Disposition of Criticality Control Overpacks at the Waste Isolation Pilot Plant

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