This report provides information on the inventory of spent nuclear fuel (SNF) in the United States located at Nuclear Power Reactor and Independent Spent Fuel Storage Installation sites, as well as SNF and reprocessing waste located at U.S. Department of Energy sites and other research and development centers as of the end of calendar year 2021.
Stress corrosion cracking (SCC) of welded stainless steel dry storage canisters may potentially impact systems exposed to corrosive atmospheric elements, such as those occurring near salt water bodies. Conditions important for atmospheric-related SCC include concentration and chemical species of the contaminants, temperature, and humidity. Calvert Cliffs Nuclear Power Plant conducted this historically important first inspection of spent fuel canisters to collect data for an SCC evaluation as part of the EPRI-led Extended Storage Collaboration Program (ESCP).
The purpose of this design analysis is to determine the accuracy of the SAS2H module of SCALE 4.3 in predicting isotopic concentrations of spent fuel assemblies. The objective is to develop a methodology for modeling assemblies similar to those evaluated within this analysis and to establish the consistency of SAS2H predictions. The results of this analysis may then be applied to future depletion calculations using SAS2H in which no measurements are available.
Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI
As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Station’s Independent Spent Fuel Storage Installation (ISFSI). The inspection procedure included surface temperature measurements on one end of the DSC within the storage module.
THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL
The work reported here is an investigation of the sensitivity of component temperatures in a specific storage system, including fuel cladding temperatures, in response to modeling assumptions that differ from design-basis, including age-related changes that could degrade the thermal behavior of the system. Preliminary evaluations of representative horizontal and vertical storage systems at design basis conditions provides general insight into the expected behavior of storage systems over extended periods of time.