L P Miller Contact millerlp@ornl.gov All Publications Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations Validation of UNF-ST&DARDS Decay Heat Calculations for BWR Fuel Validation of UNF-ST&DARDS Criticality Calculations for BWR Fuel UNF-ST&DARDS: A UNIQUE TOOL FOR SPENT NUCLEAR FUEL CHARACTERIZATION AND LONG-TERM FUEL DATABASE MANAGEMENT Dual Purpose Canister Reactivity and Groundwater Absorption Analyses NEAMS Workbench MOOSE Integration Update Demonstration of the On-the-Fly Shielding Analysis Method Basket Modification Concepts for Disposal Reactivity Control of Dual Purpose Canisters NEAMS Workbench Status and Capabilities Dual Purpose Canister Reactivity and Groundwater Absorption Analyses... FINAL Report For Project TCF-18-15778 Criticality Analysis for Direct Disposal of Dual-Purpose Canisters NEAMS Workbench and Bison Fuel Performance Remote Application Configuration A Misload Analysis Methodology Supporting Criticality Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations NEAMS Workbench Status and Capabilities Criticality Safety Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations CONTAINMENT ANALYSIS CAPABILITY OF UNF-ST&DARDS Thermal Analysis Capability of UNF-ST&DARDS Development of Streamlined Nuclear Safety Analyses for Used Nuclear Fuel Applications Shielding Analysis Capability Of UNF-ST&DARDS UNF-ST&DARDS Unified Database and the Automatic Document Generator Consolidating Spent Nuclear Fuel Related Data into a Unified Database... UNF-ST&DARDS: A Unique Tool for Automated Characterization of Spent Nuclear Fuel and Related Systems... Containment Analysis Capability of UNF-ST&DARDS... Shielding Analysis Capability of UNF-ST&DARDS... Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » Key Links
