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 Criticality Calculations for BWR Fuel Validation of UNF-ST&DARDS Decay Heat 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 FINAL Report For Project TCF-18-15778 NEAMS Workbench Status and Capabilities Dual Purpose Canister Reactivity and Groundwater Absorption Analyses... Criticality Analysis for Direct Disposal of Dual-Purpose Canisters 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 NEAMS Workbench and Bison Fuel Performance Remote Application Configuration UNF-ST&DARDS Unified Database and the Automatic Document Generator 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 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
