In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites.
This report documents experimental work evaluating localized corrosion of container and canister materials performed at Sandia National Laboratories. The report also documents the results of analyses of the dust samples collected by the EPRI-led in-service inspections of dry storage canisters at existing ISFSIs (Hope Creek NJ, and Diablo Canyon CA).
The objective of the Crystalline Disposal R&D work is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and computational capabilities to evaluate various disposal concepts in such media. The major accomplishments during the year include: 1) R&D plan was developed for used fuel disposal in crystalline rocks; 2) established a generic reference case for crystalline disposal media; 3) developed and applied THMC models to the analysis of coupled EBS processes in bentonite-backfilled repositories; 4) examined t
This report provides a status of the performance of a systematic study of used nuclear fuel (UNF, also known as “spent nuclear fuel” [SNF]) integrity under simulated transportation environments using the Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT) hot-cell testing technology developed at Oak Ridge National Laboratory (ORNL) in August 2013. Under Nuclear Regulatory Commission (NRC) sponsorship, ORNL completed four benchmark tests, four static tests, and twelve dynamic or cycle tests on H. B. Robinson (HBR) high burn-up (HBU) fuel.
The purpose of this research effort is to determine the effects of canister/cask vacuum drying and storage on radial hydride precipitation in high‐burnup (HBU) pressurized water reactor (PWR) cladding alloys during cooling for a range of peak drying‐storage temperatures, internal gas pressures, and hoop stresses. The HBU PWR cladding alloys have a wide range of hydrogen contents and varying hydride morphology after in‐reactor service.
This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. To date, UFD’s International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several international partners, and has started several specific collaborative R&D activities. These international activities include testing and modeling studies and address the following key research areas: Near-Field Perturbation, Engineered Barrier Integrity, Radionuclide Transport, and
The report describes implementation and planning of websites that allow visualization or manipulation of data in the UFD GIS Database; e.g., the distribution of crystalline rock, basement depth, and salt and shale formations within the contiguous United States, and visualizations of the relationships between geologic media and selected natural and cultural features pertaining to potential siting guidelines for repository siting.
This report documents the development, demonstration and validation of a mesoscale, microstructural evolution model for simulation of zirconium hydride d-ZrH1.5 precipitation in the cladding of used nuclear fuels that may occur during long-term dry storage. The precipitation and growth of zirconium hydrides during dry storage is one of the most likely fuel rod integrity failure mechanisms either by embrittlement or delayed hydride cracking of the cladding. The model being documented in this work is a computational capability for the prediction of hydride formation in different claddings
This report describes a test of an instrumented surrogate PWR fuel assembly on a truck trailer conducted to simulate normal conditions of truck transport. The purpose of the test was to measure strains and accelerations on a Zircaloy-4 fuel rod during the transport of the assembly on the truck. This test complements tests conducted in FY13 in which the same assembly was placed on a shaker and subjected to vertical vibrations and shocks simulating truck transport. The strains measured on the instrumented Zircaloy-4 rod over a 40.2 mile route never exceeded 150 μin./in.
Radioactive waste disposal in shale/argillite rock formations has been widely considered given its desirable isolation properties, e.g., low permeability, potential geochemically reduced conditions, anomalous groundwater pressures, and widespread geologic occurrence.
The collaborative approach to the glass and metallic waste form degradation modeling activities includes process model development (including first-principles approaches) and model integration—both internally among developed process models and between developed process models and PA models, and cross campaign integration between activities in the Used Fuel Disposition (UFD) Campaign and the Separations (to be Materials Recovery) and Waste Forms (SWF=>MRWF) Campaign. Experimental work is conducted within the UNFD area and results are utilized in development efforts. The primary outputs
The Nuclear Energy Advanced Modeling and Simulation (NEAMS) quarterly report includes updates, highlights, fuels and reactors product line accomplishments, integration accomplishments, recent and upcoming milestones.
The determination covers the Department’s sales or transfers of no more than 2,705 metric tons (MTU) of natural uranium (NU) or NU equivalent in a calendar year. The proposed transfers include up to 650 MTU per year by the National Nuclear Security Administration in support of highly enriched uranium down blending activities, with the remainder of up to 2,705 MTU per year supporting accelerated cleanup activities by the Office of Environmental Management.
Energy Resources International (ERI), Inc conducted this independent market impact analysis on DOE planned uranium sales and transfers during the period 2014 to 2033, based on information concerning quantities and schedules provided to ERI by DOE.
[In Support of a Comprehensive National Nuclear Fuel Cycle Strategy, Volumes I and II (Appendices)]
This study provides a technical basis for informing policy decisions regarding strategies for the management and permanent disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) in the United States requiring geologic isolation.