Publications
Showing 120 results for Author: Robert A. Lefebvre
Dec, 2014
Conference Paper
Modernization Enhancements in SCALE 6.2
SCALE is a widely used suite of tools for nuclear systems modeling and simulation that provides comprehensive, verified and validated, user-friendly capabilities for criticality safety, reactor physics, radiation shielding, and sensitivity and uncertainty analysis. For more than 30 years, regulators, industry, and research institutions around the world have used SCALE for…
Dec, 2014
Conference Paper
POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System
Nov, 2014
Conference Paper
The Used Nuclear Fuel Storage, Transportation, and Disposal Analysis Resource and Data System
Jul, 2014
Conference Paper
Dose Rate Analysis Capability for Actual Spent Fuel Transportation Cask Contents
The approved contents for a U.S. Nuclear Regulatory Commission (NRC) licensed spent nuclear fuel casks are typically based on bounding used nuclear fuel (UNF) characteristics. However, the contents of the UNF canisters currently in storage at independent spent fuel storage installations are considerably heterogeneous in terms of fuel assembly burnup, initial enrichment, de…
Nov, 2013
ORNL Report
Safety Margin Assessment For Maine Yankee, Connecticut Yankee, and Rancho Seco Casks