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Applicability of CRC Benchmark Experiments for Burnup Credit Validation
Applicability of CRC Benchmark Experiments for Burnup Credit Validation
Axial Burnup Profile Database for Pressurized Water Reactors
Axial Burnup Profile Database for Pressurized Water Reactors
The data were obtained directly from utilities whose reactors represent the range of commercial PWR fuel lattices. The work was performed by Yankee Atomic Electric for Sandia National Laboratory. All axial burnup profiles were calculated from 3-D depletion analyses of the core configuration. The organizations and utilities providing axial burnup profiles for the database used different model codes for the 3D-depletion calculations. The model codes used were: SIMULATE-3, NEMO, ANC, and PRESTO-II. Cross-section inputs describing the assemblies are derived from assembly lattice calculations.
Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation
Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs
Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs
Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation
Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation
PWR Burnup Credit Using Both Belts and Suspenders
PWR Burnup Credit Using Both Belts and Suspenders
Status of the Joint French ISPN/COGEMA Qualification Programme of Fission Products
Status of the Joint French ISPN/COGEMA Qualification Programme of Fission Products
Design of Wet Storage Racks for Spent BWR Fuel
Design of Wet Storage Racks for Spent BWR Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
2015 NEI Used Fuel Management Conference Presentations
2015 NEI Used Fuel Management Conference Presentations
Link to NEI's website where the 2015 NEI Used Fuel Management Conference presentations can be downloaded.
Day 1
Session 0, Opening Plenary
Korsnick, Maria
Exelon Generation
Nuclear Energy in a Changing Marketplace
Lombard, Mark
U.S. Nuclear Regulatory Commission
NRC Management Perspective: What’s Up?
McCullum, Rod
Nuclear Energy Institute
Management Perspectives
Session 1, Used Fuel Policy
Nuclear Fuels Storage and Transportation Planning Project (NFST) System Analysis Models
Nuclear Fuels Storage and Transportation Planning Project (NFST) System Analysis Models
Animated slide show of Nuclear Fuels Storage and Transportation Planning Project (NFST) System Analysis Models. Runs in Microsoft PowerPoint slide show. Run time is 12 minutes.
WCS Files License Application with Nuclear Regulatory Commission (NRC) to Operate a Consolidated Interim Storage Facility (CISF) for Used Nuclear Fuel
WCS Files License Application with Nuclear Regulatory Commission (NRC) to Operate a Consolidated Interim Storage Facility (CISF) for Used Nuclear Fuel
WASHINGTON, D.C. (April 28, 2016) – Waste Control Specialists LLC (WCS) submitted an application to the Nuclear Regulatory Commission (NRC) for a license to construct and operate a Consolidated Interim Storage Facility (CISF) for used nuclear fuel. The filing comes after a year of pre-application meetings with NRC and maintains the timeline WCS outlined in February 2015.
The application is being led by WCS, along with its partners AREVA and NAC International, both global industry leaders in the transportation and storage of used nuclear fuel.
WCS Presentation Slides to NRC 8-22-16
WCS Presentation Slides to NRC 8-22-16
WCS Presentation slides for NRC meeting held 8-22-16 to discuss the status of responses to NRC Requests for Supplemental Information.
Sister Rod Examinations at ORNL for the HBU Spent Fuel Data Project
Sister Rod Examinations at ORNL for the HBU Spent Fuel Data Project
Presentation made at the Electric Power Research Institute (EPRI) Extended Storage Collaboration Project (ESCP) meeting November 2016 discussing the status of nondestructive examinations being performed on high burnup (HBU) sent nuclear fuel (SNF) rods at Oak Ridge National Laboratory and proposed destructive examinations that will be performed over the next several years.
Execution Strategy Analysis Conference Papers
Execution Strategy Analysis Conference Papers
Conference papers on the IWM Execution Strategy Analysis process and tool.
Does Consolidated Interim Storage Make Sense in an Integrated Waste Management System?
Does Consolidated Interim Storage Make Sense in an Integrated Waste Management System?
Presentation given at the NEI Used Fuel Management Conference in Savannah, Georgia on May 3, 2017. It discusses advantages and disadvantages of consolidated interim storage as well as highlights recent work related to the economics of consolidated storage.
Development of Rail Accident Rates for SNF Rail Shipments
Development of Rail Accident Rates for SNF Rail Shipments
Presentation and Paper for WM 2017. A key factor in evaluating the safety of rail shipments involving the transport of commercial spent nuclear fuel (SNF) is the development of transportation accident rates that are reflective of the unique characteristics associated with these train operations. Typical rail freight operations may involve consists of a hundred cars or more, which may pass through multiple rail yards for trains to be decoupled and reassembled. In contrast, trains carrying SNF are anticipated to be operated in consists of considerably fewer cars.
Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel (2024)
Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel (2024)
This report fulfills the M3 milestone M3SF-23PN0203020614, “Updated NPP Site Evaluation Report (2).” This report is an update of the 2021 report Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel and includes expansion of the site evaluations to include operating nuclear power plant (NPP) sites and to incorporate updated site inventory data. Figures that include the number of spent nuclear fuel (SNF) assemblies and metric tons heavy metal (MTHM) in a single figure have also been added to the report.
Let the Talk Count: Attributes of Stakeholder Engagement, Trust, Perceive Environmental Protection and CSR
Let the Talk Count: Attributes of Stakeholder Engagement, Trust, Perceive Environmental Protection and CSR
This article tests the links between attributes of stakeholder engagement (information sharing [quantity and quality of information sharing], procedural fairness [respectful treatment and providing voice], and empathy) and local communities’ acceptance of corporate social responsibility (CSR) initiatives with the mediating roles of trust and perceived environmental protection. Using Ghana as a case, survey data were collected from 604 local inhabitants in mining communities for the study.