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slides - Generic Communications and Guidance on Spent Fuel Storage & Transportation
slides - Generic Communications and Guidance on Spent Fuel Storage & Transportation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Cook Nuclear Plant, Dry Cask Loading & Storage
slides - Cook Nuclear Plant, Dry Cask Loading & Storage
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
UCF Waste Package Criticality Analysis
UCF Waste Package Criticality Analysis
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the viability of the UCF waste package concept with respect to criticality regulatory requirements in compliance with the goals of the Waste Package Implementation Plan5·1 for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives.
slides - Generic Issue Management--An Idea Taking Flight
slides - Generic Issue Management--An Idea Taking Flight
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Isotopic Models for Commercial SNF Burnup Credit
Isotopic Models for Commercial SNF Burnup Credit
Disposal Criticality Analysis Methodology Topical Report1 describes a methodology for performing postclosure criticality analyses within the repository at Yucca Mountain, Nevada. An important component of the postclosure criticality analysis is the calculation of conservative isotopic concentrations for spent nuclear fuel. This report documents the isotopic calculation methodology. The isotopic calculation methodology is shown to be conservative based upon current data for pressurized water reactor and boiling water reactor spent nuclear fuel.
U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks
U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks
In July 1999, the U.S. Nuclear Regulatory Commission (NRC) Spent Fuel Project Office
(SFPO) issued Interim Staff Guidance 8 Revision 1 (ISG8R1) to provide recommendations for the use
of burnup credit in storage and transport of pressurized-water reactor (PWR) spent fuel. Subsequent to
the issuance of ISG8R1, the NRC Office of Regulatory Research (RES) has directed an effort to
investigate the technical basis for extending the criteria and recommendations of ISG8R1 to allow
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
44-BWR WASTE PACKAGE LOADING CURVE EVALUATION
44-BWR WASTE PACKAGE LOADING CURVE EVALUATION
The objective of this calculation is to evaluate the required minimum burnup as a function of initial boiling water reactor (BWR) assembly enrichment that would permit loading of spent nuclear fuel into the 44 BWR waste package configuration as provided in Attachment IV. This calculation is an application of the methodology presented in ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent (wt%) U-235, and a burnup range of 0 through 40 GWd/MTU.
Waste Package Probabilistic Criticality Analysis: Summary Report of Evaluations in 1997
Waste Package Probabilistic Criticality Analysis: Summary Report of Evaluations in 1997
The purpose of this document is to summarize the degraded waste package disposal criticality evaluations which were reported in FY 1997 (Refs. 2-6), and to explain how those evaluations have served to further develop various aspects of the overall methodology for such evaluations.
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 - 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
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
End Effect keff Cias Curve for Actinide-Only Burnup Credit Casks
End Effect keff Cias Curve for Actinide-Only Burnup Credit Casks
A conservative end effect keff bias curve for actinide-only burnup credit casks is presented
in this paper. Rather than performing axially burnup-dependent analysis, cask designers can, if
they choose to, analyze casks with a uniform axial burnup (at assembly average burnup value) and
add the keff bias values to conservatively bound the actinide-only end effect. Earlier studies
suggested 1-3% increase in keff to account for the end effect, but they included fission products
as well as actinides for their analyses.
slides GC-859 Pilot
slides GC-859 Pilot
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Calculation of Isotopic Bias and Uncertainty for BWR SNF
Calculation of Isotopic Bias and Uncertainty for BWR SNF
The objective of Calculation of Isotopic Bias and Uncertainty for BWR SNF is to quantify the computational bias and uncertainty in the multiplication factor (keff) to be used for Boiling Water Reactor (BWR) spent nuclear fuel (SNF) burn-up credit. The scope of this bias and uncertainty determination covers 38 different radiochemical assay (RCA) spent fuel samples from 14 different fuel assemblies that were irradiated in four different BWRs. The irradiated fuel samples evaluated span an enrichment range of 2.53 weight percent U-235 through 3.95 weight percent U-235.
slides - Industry Response to NRC's Request for Comments on Retrievability, Cladding Integrity and 10 CFR 71/72 Alignment
slides - Industry Response to NRC's Request for Comments on Retrievability, Cladding Integrity and 10 CFR 71/72 Alignment
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Potential Improvements to the Licensing Process for a Recycling Plant
slides - Potential Improvements to the Licensing Process for a Recycling Plant
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Slides - Status Update: Extended Storage and Transportation Waste Confidence
Slides - Status Update: Extended Storage and Transportation Waste Confidence
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - GC-859 Pilot Program Update
slides - GC-859 Pilot Program Update
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - DOE Nuclear Fuel Storage and Transportation (NFST) Planning Project: System Analysis and Integration Activities
slides - DOE Nuclear Fuel Storage and Transportation (NFST) Planning Project: System Analysis and Integration Activities
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
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