Active participation in international R&D is crucial for achieving the Used Nuclear Fuel Disposition long-term goals of conducting experiments to fill data needs and confirm advanced modeling approaches and of having a robust modeling and experimental basis for evaluation of multiple disposal system options.
This report documents the first phase of a multi-year project to understand the technical feasibility and logistical implications of direct disposal of spent nuclear fuel in existing dual-purpose canisters (DPCs) and other types of storage casks.
Contributions are described for the development of an enhanced generic disposal system modeling and analysis capability that takes advantage of high-performance computing (HPC) environments to simulate the important multi-physics phenomena and couplings associated with a geologic repository for UNF and HLW.
Deep borehole disposal is one alternative for the disposal of spent nuclear fuel and other radioactive waste forms; identifying a site or areas with favorable geological, hydrogeological, and geochemical conditions is one of the first steps to a demonstration project.
The report describes the strategy for coupling process level models to produce an integrated Used Fuel Degradation Model (FDM), and addresses fractional degradation rate, instant release fractions, other continuum modeling approaches, and experimental support.
This report provides results of the initial demonstration of the modeling capability developed to perform preliminary deterministic evaluations of moderate-to-high burnup used nuclear fuel (UNF) mechanical performance under normal conditions of storage (NCS) and transport (NCT).
This study contributes to investigation and better understanding of cladding (High Flux Isotope Reactor used to simulate the effects of high burnup on fuel cladding) materials performance in extended storage and transportation through the conduct of small scale and separate effects tests (SET).
Enginerred Barrier Systems (EBS) model evaluation and development is fundamental to the design and analysis of disposal concepts for generic repository systems; this report centers on progress made on modeling and experimental approaches to analyze physical and chemical interactions affecting clay barrier performance.
Experiments were used to examine water content in Permian salt samples including impact of variation in thermal regime on water content of evaporites and other mineral species, behavior of brine inclusions in salt, and evolution of the gas/liquid brine/salt system.
This work on the natural barrier system is conducted to reduce uncertainty in natural system performance and to fully exploit the credits that can be taken for the natural system barrier; several potential enhancements to describing barrier performance capabilities are presented.
Shale and clay-rich rock formations have been considered as potential host rocks for geological disposal of high-level radioactive waste throughout the world: modeling thermal, hydrological, mechanical, and chemical (THMC) of the near field of generic clay repository is discussed.
The Generic Deep Geologic Disposal Safety Case presents generic information that is of use in understanding potential deep geologic disposal options (e.g., salt, shale, granite, deep borehole) in the U.S. for used nuclear fuel (UNF) from reactors and high-level radioactive waste (HLW).
The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis.
Results of testing employing surrogate instrumented rods (non-high-burnup, 17 x 17 PWR fuel assembly) to capture the response to the loadings experienced during normal conditions of transport indicate that strain- or stress-based failure of fuel rods seems unlikely; performance of high-burnup fuels continues to be assessed.
This report describes RD&D activities to support a safety case for disposal of heat generating radioactive waste (used nuclear fuel, high-level nuclear waste) in a generic bedded salt repository based on interactions from March, 2013 Workshop.
This report evaluates existing capabilities at Idaho National Laboratory (INL) to determine if a practical and cost effective method could be developed for handling and opening full-sized dry storage casks in support of the U.S. Department of Energy's plan for confirmatory dry storage project for high burnup fuel.
Used nuclear fuel (UNF) must maintain its integrity during the storage period in such a way that it can withstand the physical forces of handling and transportation associated with restaging the fuel and transporting it to treatment or recycling facilities, or to a geologic repository.
Clay and granitic geologic rock units are potential host media for future repositories for used nuclear fuel and high level waste. This report addresses the representation of flow in these two media within numerical process (discrete fracture network) models.
The Office of Nuclear Energy has conducted a technical review and assessment of the total current inventory [~70,150 MTHM as of 2011] of domestic discharged used nuclear fuel (UNF) and estimated an amount to be considered for retention in support of research, development, demonstration, and national security interests.