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Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit
Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit
The effect of fixed absorbers on the reactivity of pressurized water reactor (PWR) spent nuclear fuel (SNF) in support of burnup-credit criticality safety analyses is examined. A fuel assembly burned in conjunction with fixed absorbers may have a higher reactivity for a given burnup than an assembly that has not used fixed absorbers. As a result, guidance on burnup credit, issued by the U.S. Nuclear Regulatory Commission's Spent Fuel Project Office, recommends restricting the use of burnup credit to assemblies that have not used burnable absorbers.
Used Fuel Management System Interface Analyses
Used Fuel Management System Interface Analyses
Preliminary system-level analyses of the interfaces between at-reactor used fuel management, consolidated storage facilities, and disposal facilities, along with the development of supporting logistics simulation tools, have been initiated to provide the U.S. Department of Energy (DOE) and other stakeholders with information regarding the various alternatives for managing used nuclear fuel (UNF) generated by the current fleet of light water reactors operating in the United States.
Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy
Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy
A technical assessment of the current inventory [~70,150 metric tons of heavy metal (MTHM) as of
2011] of U.S.-discharged used nuclear fuel (UNF) has been performed to support decisions regarding fuel
cycle strategies and research, development and demonstration (RD&D) needs. The assessment considered
discharged UNF from commercial nuclear electricity generation and defense and research programs and
determined that the current UNF inventory can be divided into the following three categories:
Dry Cask Storage of Nuclear Spent Fuel
Dry Cask Storage of Nuclear Spent Fuel
Dry Cask Storage of Nuclear Spent Fuel
Dry Cask Storage of Nuclear Spent Fuel
This presentation was given by Earl Easton at the 2011 National State Liaison Officers Conference in Bethesda, MD.
The presentation highlights the current state of spent nuclear fuel as well as the progress toward its ultimate disposal.
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.
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
This paper presents an evaluation of the amount of burnup credit needed for high-density casks to
transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic
32-assembly cask and the current regulatory guidance were used as bases for this evaluation.
By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial
enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based
slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters
slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013