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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.
Transportation of Commercial Spent Nuclear Fuel Regulatory Issues Resolution
Transportation of Commercial Spent Nuclear Fuel Regulatory Issues Resolution
The U.S. industry’s limited efforts at licensing transportation packages characterized as “highcapacity,”
or containing “high-burnup” (>45 GWd/MTU) commercial spent nuclear fuel
(CSNF), or both, have not been successful considering existing spent-fuel inventories that will
have to be eventually transported. A holistic framework is proposed for resolving several CSNF
transportation issues. The framework considers transportation risks, spent-fuel and cask-design
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
Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel
Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel
This report investigates trends in the radiological decay properties and changes in relative nuclide importance associated with increasing enrichments and burnup for spent LWR fuel as they affect the areas of criticality safety, thermal analysis (decay heat), and shielding analysis of spent fuel transport and storage casks. To facilitate identifying the changes in the spent fuel compositions that most directly impact these application areas, the dominant nuclides in each area have been identified and ranked by importance.
EBS Radionuclide Transport Abstraction
EBS Radionuclide Transport Abstraction
The purpose of this report is to develop and analyze the Engineered Barrier System (EBS) Radionuclide Transport Abstraction Model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment: Engineered Barrier System: Radionuclide Transport Abstraction Model Report (BSC 2006 [DIRS 177739]). The EBS Radionuclide Transport Abstraction (or RTA) is the conceptual model used in the Total System Performance Assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ).
Extended Storage and Transportation - Evaluation of Drying Adequacy
Extended Storage and Transportation - Evaluation of Drying Adequacy
The U.S. Nuclear Regulatory Commission (NRC) is evaluating the safety and security of spent nuclear fuel (SNF) stored in dry casks for extended time periods before transportation to a location where the SNF is further processed or permanently disposed.
slides - Certification/Licensing Approaches for High Burnup Spent Fuel
slides - Certification/Licensing Approaches for High Burnup Spent Fuel
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - EPRI High Burnup Used Fuel Confirmatory Demonstration Project [The "High Burnup Demo"]
slides - EPRI High Burnup Used Fuel Confirmatory Demonstration Project [The "High Burnup Demo"]
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013