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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 1,135 records · Page 63

Comparative Cost Analysis of Spent Nuclear Fuel Management Alternatives

This report presents a comparative analysis of spent nuclear fuel management options to support the U.S. Department of Energy (DOE). Specifically, a set of scenarios was constructed to represent a range of possible combinations of alternative spent fuel management approaches. Analyses were performed to provide simple and credible estimates of relative costs to the U.S. government and to the nuclear utilities for moving forward with each scenario. The analyses of alternatives and options related to spent nuclear fuel management presented in this report are based on technical and programmatic considerations and do not include an evaluation of relevant regulatory and legal considerations (e.g., needs for new or modified regulations or legislation). This report has been prepared for informational and comparison purposes only and should not be construed as a determination of the legal permissibility of specific alternatives and options. No inferences should be drawn from this report regarding future actions by DOE. To the extent this report conflicts with provisions of the Standard Contract, those provisions prevail.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Overview of the U.S.-U.K. Portal Monitor for Authentication and Certification (PMAC) Project [Slides]

The PM designed and demonstrated under the PMAC project is a significant improvement from other existing PMs in terms of the joint host / inspector confidence provided and usability in a future hypothetical arms control regime. Based on these results, the PMAC system would be the best option currently available for a boundary control use case in a hypothetical arms control regime.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Integration of the Back End of the Nuclear Fuel Cycle

Management of spent nuclear fuel and high-level radioactive waste consists of three main phases – storage, transportation, and disposal – commonly referred to as the back end of the nuclear fuel cycle. Current practice for commercial spent nuclear fuel management in the United States (US) includes temporary storage of spent fuel in both pools and dry storage systems at operating or shutdown nuclear power plants. Storage pools are filling to their operational capacity, and management of the approximately 2,200 metric tons of spent fuel newly discharged each year requires transferring older and cooler spent fuel from pools into dry storage. Unless a repository becomes available that can accept spent fuel for permanent disposal, projections indicate that the US will have approximately 136,000 metric tons of spent fuel in dry storage systems by mid-century, when the last plants in the current reactor fleet are decommissioned. Current designs for dry storage systems rely on large multi-assembly canisters, the most common of which are so-called “dual-purpose canisters” (DPCs). DPCs are certified for both storage and transportation, but are not designed or licensed for permanent disposal. The large capacity (greater number of spent fuel assemblies) of these canisters can lead to higher canister temperatures, which can delay transportation and/or complicate disposal. This current management practice, in which the utilities continue loading an ever-increasing inventory of larger DPCs, does not emphasize integration among storage, transportation, and disposal. This lack of integration does not cause safety issues, but it does lead to a suboptimal system that increases costs, complicates storage and transportation operations, and limits options for permanent disposal. This paper describes strategies for improving integration of management practices in the US across the entire back end of the nuclear fuel cycle. The complex interactions between storage, transportation, and disposal make a single optimal solution unlikely. However, efforts to integrate various phases of nuclear waste management can have the greatest impact if they begin promptly and continue to evolve throughout the remaining life of the current fuel cycle. A key factor that influences the path forward for integration of nuclear waste management practices is the identification of the timing and location for a repository. The most cost-effective path forward would be to open a repository by mid-century with the capability to directly dispose of DPCs without repackaging the spent fuel into disposalready canisters. Options that involve repackaging of spent fuel from DPCs into disposalready canisters or that delay the repository opening significantly beyond mid-century could add 10s of billions of dollars to the total system life cycle cost.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations

This report presents Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations prepared for the National Nuclear Security Administration (NNSA) Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D) Safeguards Program by a multilaboratory team from Oak Ridge National Laboratory, Los Alamos National Laboratory, and Y-12 National Security Complex. It documents key findings of a 2-year scoping study on “Safeguards Technology Needs Assessment for Leading Thorium Fuel Cycles” (project OR18-V-SG Tec Needs Th Fuel Cycles-PD1Lb).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Ta compressibility to 20+ Mbar

Developing techniques for experimentally constraining equation of state (EOS) models for important programmatic materials under extreme conditions is vital for advancing our modeling and predictive capabilities. Tantalum is a frequently used standard material for both calibration and testing, and this report describes our work to both measure Ta compressibility to very high pressures and densities using the Ramp Compression Equation of State platform on the National Ignition Facility (NIF). Using a series of seven shots, increasing in peak pressure with each shot, we have made absolute measurements of the compressibility of Ta along the ramp compression path up to 2.3 TPa. Previous experimental measurements constrained the cold compressibility up to ~400 GPa, and there is a spread in the EOS models above that pressure. To improve communication and collaboration between the experimental team and the EOS development group, these new data, along with other experimental and theoretical constraints, were used to develop a Ta equation of state table, M73000. This report first describes the experimental measurements made at the NIF, and then discusses the construction of the EOS model. The ramp compression data can be found in tabular form in Appendix A. Appendix B contains some additional experimental details. In Appendix C we include some additional details on the EOS modeling. At the end of this document, we have attached a detailed report on the NIF ramp compression platform itself and in the main text referenced specific sections for additional details.

36 MATERIALS SCIENCE↗

Advanced Laboratory and Field Arrays: Accelerate the development of next-generation marine energy conversion systems (Task 3)

This task successfully improved the representation of extreme conditions in wave resource characterization. The previous state of the art to characterize extreme conditions was a purely statistical representation of buoy data; Generalized Extreme Value (GEV) techniques are used to extrapolate joint histograms of significant wave height Hs and energy period T e for a given return period. The task confirmed that H s and T e alone are a poor representation of the actual hazards in extreme events, during which WECs many experience significant impacts from wave groups and breaking waves (i.e., it is not simply the largest wave that may produce the worst condition for a WEC). This task improved both prediction of extreme conditions with “third generation” spectral models, such as WAVEWATCHIII and WAM, and observational quantification of the wave breaking impacts during extreme conditions.

13 HYDRO ENERGY↗