Category of Content
Siting Experience Documents Only
Publication Date
Country
Keywords
slides - Operating Experience, Session I, Cask Cranes
slides - Operating Experience, Session I, Cask Cranes
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Infrastructure
slides - Transportation Infrastructure
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Readiness
slides - Transportation Readiness
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Vendor Perspective on Spent Fuel Pool Criticality Analysis
slides - Vendor Perspective on Spent Fuel Pool Criticality Analysis
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Cumulative Impact of Industry and NRC Actions
slides - Cumulative Impact of Industry and NRC Actions
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Abstraction of Drift Seepage
Abstraction of Drift Seepage
This model report documents the abstraction of drift seepage, conducted to provide seepage relevant parameters and their probability distributions for use in Total System Performance Assessment for License Application (TSPA-LA). Drift seepage refers to the flow of liquid water into waste emplacement drifts.
Slides - Retrievability, Cladding Integrity, and Safety Handling during Storage and Transportation
Slides - Retrievability, Cladding Integrity, and Safety Handling during Storage and Transportation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Evaluation of Waste Stream Receipt Scenarios for Repository Loading
Evaluation of Waste Stream Receipt Scenarios for Repository Loading
The purpose of this calculation is to simulate the processing of an incoming waste stream into waste packages, simulating the required aging as applicable, and the emplacement of the waste packages into the Yucca Mountain repository.
slides - Observations on Key Storage and Transport Technical Issues
slides - Observations on Key Storage and Transport Technical Issues
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Planning Considerations: BRC Report Recommendations and Plans for Implementation
slides - Transportation Planning Considerations: BRC Report Recommendations and Plans for Implementation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Readiness
slides - Transportation Readiness
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Advancing the Used Fuel Management Agenda
slides - Advancing the Used Fuel Management Agenda
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Flexible Integrated Modular Nuclear Fuel Canister System
Flexible Integrated Modular Nuclear Fuel Canister System
Slides, Spark Presentation
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.
Partnering for Long-term Management of Radioactive Waste-Evolution and Current Practice in Thirteen Countries
Partnering for Long-term Management of Radioactive Waste-Evolution and Current Practice in Thirteen Countries
Drift Scale THM Model
Drift Scale THM Model
This model report documents the drift scale coupled thermal-hydrological-mechanical (THM) processes model development and presents simulations of the THM behavior in fractured rock close to emplacement drifts. The modeling and analyses are used to evaluate the impact of THM processes on permeability and flow in the near-field of the emplacement drifts.
slides - Corrosion Monitoring of a Natural Convection Cooled Stored
slides - Corrosion Monitoring of a Natural Convection Cooled Stored
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Dominion Work Related to High Burn-up Fuel Demonstration Project
slides - Dominion Work Related to High Burn-up Fuel Demonstration Project
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Fukushima Dai-ichi NPS Defueling Status
slides - Fukushima Dai-ichi NPS Defueling Status
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Management of Spent Fuel Pool Neutron Absorbing Material Degradation
slides - Management of Spent Fuel Pool Neutron Absorbing Material Degradation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Thermal Management Flexibility Analysis
Thermal Management Flexibility Analysis
The purpose of this report is to demonstrate that postclosure temperature limits can be met, and certain thermal characteristics of the postclosure thermal reference case can be preserved, with alternative thermal loading schemes. The analysis considers certain variations from the base case.waste stream, the predicted postclosure temperatures that develop within the rock mass due to these waste stream variations, and then compares these temperatures to postclosure temperature limits.
slides - Ideas for Obtaining Near-Term High Burn-up Used Fuel Data
slides - Ideas for Obtaining Near-Term High Burn-up Used Fuel Data
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
This calculation is prepared by the Monitored Geologic Repository Waste Package Requirements & Integration Department. The purpose of this calculation is to compile source term and commercial waste stream information for use in the analysis of waste package (WP) designs for commercial fuel. Information presented will consist of the number of WPs, source terms, metric tons of uranium, and the average characteristics of assemblies to be placed in each WP design. The source terms provide thermal output, radiation sources, and radionuclide inventories.