Riley Cumberland Research and Development Staff Member Contact CUMBERLANDRM@ORNL.GOV All Publications Core Physics Characteristics of Extended Enrichment and High Burnup Boiling Water Reactor Fuel Core Physics Characteristics of Extended Enrichment and Higher Burnup Boiling Water Reactor Fuel Simulations of Water Flow in Relation to a Steady Criticality in an Unsaturated Alluvial Repository... Development of Shielding Benchmarks Using the Godiva IV Assembly Dual-Purpose Canister Filling Facility Concept Report GDSA - Modeling and Integration – ORNL: PFLOTRAN modeling Post-closure Nuclear Criticality Safety Evaluations for Disposition of Criticality Control Overpacks at the Waste Isolation Pilot Plant Criticality Accident Alarm System Shielding Benchmark: Integral Experiment Request 498, Critical Engineering Decision 2 Report Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol II: BWR Fuel An Analysis of Potentially Implementing Standardized Canisters in the U.S. Commercial Waste Management System Sensitivity Study on Potential Interim Storage Facility Capacities for US Spent Nuclear Fuel Comparison of Decay Time Constraints Affecting Transport of Spent Nuclear Fuel Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol I: PWR fuel Effects on Estimated External Dose Rate from Loss of Lead Shielding in SNF Transportation Casks An Overview of the Integrated Energy System Investigation of the Eastman Chemical Company Kingsport, Tennessee, Facility The Relationship Between Dose Rate and Decay Heat for Spent Nuclear Fuel Casks Analysis of Potential Standardized Canister Deployments at Commercial US Nuclear Reactor Sites... Integrated Energy System Investigation for the Eastman Chemical Co. Kingsport, TN Facility Trends in Dry Storage Cask Loading at Operating Reactor Sites Commercial SNF Pickup Queue Under the Standard Contact and Analysis of Hypothetical Alternate Acceptance Strategies Baselining a Spent Nuclear Fuel Cask Shielding Model UNF-ST&DARDS Unified Database and the Automatic Document Generator Standardized Canisters for Spent Nuclear Fuel: Their Potential Impact and a Proposed Path Forward Standardized Canisters and Their Potential Impact on an Integrated Waste Management System A Proposed Path Forward for Standardization Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Integrated Fuel Cycle Section Used Fuel and Nuclear Material Disposition Group
