Datamining Analysis of Rare Earth Element Recovery Research Trends - A Path Forward with Functionalized Silica Sorbents
38th Annual International Pittsburgh Coal Conference, Virtual, September 20-23, 2021
Wilfong, Walter C.↗
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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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Data Assimilation: Current use in MDD and path forward for the complex.
Abstract not provided.
Knapp, Patrick↗
Modeling the Path Forward for Marine Energy
Today's marine energy industry is at an exciting turning point. Companies are testing out their early-stage prototypes - designed to harness the clean energy in ocean and river waves, currents, and tides - in their first open-water trials. But while such trials are a necessary step toward commercialization, they can come with high costs and risk if the deployments do not go as planned.
data modeling↗
A Proposed Path Forward for Standardization - 17131
Incorporation of a standardized canister system into the commercial waste management system represents an opportunity to develop an integrated approach to storage, transportation, and disposal issues. However, regardless of timing and method, deployment of such a system would have the potential to cause significant system-wide impacts. The current inventory of commercial spent nuclear fuel dry storage systems is diverse and increasing. In addition, the currently loaded systems are large-capacity systems (up to 37 pressurized water reactor assemblies or 89 boiling water reactor assemblies) that are now able to accommodate large (greater than 45 kilowatts) amounts of heat during storage, with the potential to accommodate fairly high heat loads (∼32 kilowatts) for transportation as well. A standardized canister system designed with disposition in mind would likely be significantly smaller than the current systems and have dramatically lower heat limit maximums. Over the past few years, the Department of Energy (DOE) Office of Nuclear Energy Fuel Cycle Technologies Nuclear Fuels Storage and Transportation Planning Project (NFST) has performed a number of system analyses using logistic simulations to evaluate the impacts of incorporating these smaller canisters into the commercial waste management system. These simulations predict the amount of resources (e.g., staff, canisters/casks, rail-cars, facilities), the size of facilities, and the timing of operations, as well as provide rough order-of-magnitude cost estimates. In addition to system analyses, DOE funded efforts by EnergySolutions to develop a generic design of a small-capacity standardized canister system and investigate innovative operational approaches to minimize the at-reactor operational impacts of loading such smaller canisters. A result of EnergySolutions' work was the development of a 'canister-in-carrier' concept that would allow for loading, storing, transporting, and potentially disposing of groups of small canisters at the same time. With the inclusion of this new concept, the most recent system analyses show that incorporating standardized canister systems into the commercial waste management system has the potential for some system-wide cost reductions in addition to the flexibility that smaller canisters would provide to the system. Based on these analyses, the authors of this paper recommend that DOE fund (1) a demonstration of the ability to weld up to four small canisters at the same time to confirm the feasibility and practicality of the canister-in-carrier concept and (2) the development of a more detailed conceptual design for future applications for Certificates of Compliance, if standardized canisters were incorporated into the commercial waste management system. This paper documents both the results of the latest assessment of standardized canister concepts including the canister-in-carrier concept and the authors' recommendations. (authors)
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Status of HLW disposal in the USA and rational, progressive, paths forward based upon lessons learned in the USA and abroad since 1973 - 15103
The development of the USA's only candidate (since 1987) HLW-repository at the Yucca Mountain (YM) site, Nevada, was halted by the Obama administration in 2009. Four years later, the Obama administration proposed a new strategy for the back end of the nuclear fuel cycle that would open a consent-based HLW repository 'by 2048'. At the end of 2014, both the YM HLW repository and the new HLW-disposition (storage and disposal) strategy remain on hold due to lack of enabling legislation. With this as background, and based upon our active involvement in, monitoring of, and reporting on HLW management programs in the USA and abroad since 1973, we submit that: 1. Politics, political will, and legal actions and outcomes will continue to govern progress. 2. Public acceptance and sustained support (PASS) may influence politics and political will. 3. PASS is time-dependent and governed by: a. Ideologies; b. Perceived benefits and risks; c. Level and equity of radiation protection provided by applicable regulations; d. Perceived robustness/safety of the proposed disposition concept; and e. Perceived credibility and competency vested in the involved organizations and their respective leaders (= TRUST). We therefore recommend that the USA concurrently pursues at least two, 'centralized' HLW-storage and -disposal solutions based upon best-available relevant knowledge and majority-PASS at facility-host locations. Furthermore, safe(r) and more secure disposal of defense/government-generated HLW could probably commence at least 15 years earlier than 'by 2048' in/at: 1. The YM repository/site. 2. The WIPP repository/site. 3. 'Local' deep boreholes. (authors)
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Paths Forward: Approaches to Achieve Plug and Process Load Efficiency and Control in Commercial Buildings: Preprint
To accomplish net-zero carbon in the built environment by 2050, we must equitably decarbonize commercial buildings, which includes reducing plug and process loads (PPLs). PPLs are plug-in or hardwired electric and gas loads that are not directly associated with major building end uses like lighting and heating, ventilating, and air conditioning. PPLs account for a growing portion of U.S. commercial building energy consumption. Although commercial building PPL strategies and technologies are available today, they have not been adopted at a level sufficient to achieve significant savings and load flexibility across the building stock. In our "Pathways to Plug and Process Load Efficiency and Control" study, we investigated why these technologies and strategies have not seen widespread adoption and identified five behavior and technology pathways to increase PPL reduction in commercial buildings. In this paper, we expand beyond identifying the pathways and discuss approaches for achieving them. We discuss the importance of collecting and sharing data and case studies on PPL energy consumption and savings from control technology implementation, including code-required measures, for increasing adoption. Centralizing case studies and data, engaging industry organizations, and promoting awareness of PPL efficiency benefits to relevant groups are also key approaches. Additionally, funding, incentives, and rebate programs play important roles in driving PPL efficiency and control adoption. Finally, we discuss integrating PPL efficiency into broader company goals, such as environmental, social and governance (ESG) strategies and green building certifications, to further drive adoption.
adoption pathways↗
Model Diagnostics for Equation Oriented Models: Roadblocks and the Path Forward
Explore the source record for details and available documents.
Lee, Andrew↗
Regulatory Challenges and Potential Path Forward for Integrating Advanced Cybersecurity in Nuclear Reactors
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Gray, Titus Antonio [Sandia National Laboratories ↗
ATR Spent Fuel Options Study
The Advanced Test Reactor (ATR) is a materials and fuels test nuclear reactor that performs irradiation services for the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Naval Reactors, the National Nuclear Security Administration (NNSA), and other research programs. ATR achieved initial criticality in 1967 and is expected to operate in support of needed missions until the year 2050 or beyond. It is anticipated that ATR will generate approximately 105 spent nuclear fuel (SNF) elements per year through the year 2050. Idaho National Laboratory (INL) currently stores 2,008 ATR SNF elements in dry storage, 976 in wet storage, and expects to have 1,000 elements in wet storage before January 2017. A capability gap exists at INL for long-term (greater than the year 2050) management, in compliance with the Idaho Settlement Agreement (ISA), of ATR SNF until a monitored retrievable geological repository is open. INL has significant wet and dry storage capabilities that are owned by the DOE Office of Environmental Management (EM) and operated and managed by Fluor Idaho, which include the Idaho Nuclear Technology and Engineering Center’s (INTEC’s) CPP-666, CPP-749, and CPP-603. In addition, INL has other capabilities owned by DOE-NE and operated and managed by Battelle Energy Alliance, LLC (BEA), which are located at the Materials and Fuel Complex (MFC). Additional storage capabilities are located on the INL Site at the Naval Reactors Facility (NRF). Current INL SNF management planning, as defined in the Fluor Idaho contract, shows INTEC dry fuel storage, which is currently used for ATR SNF, will be nearly full after transfer of an additional 1,000 ATR SNF from wet storage. DOE-NE tasked BEA with identifying and analyzing options that have the potential to fulfill this capability gap. BEA assembled a team comprised of SNF management experts from Fluor Idaho, Savannah River Site (SRS), INL/BEA, and the MITRE Corp with an objective of developing and analyzing options for fulfilling the capability gap. This management options analysis is not an alternatives analysis as defined by DOE Order 413.3B; rather, it is an evaluation of near-term, mid term and long-term actions needed to fulfill the capability gap. The actions are described in sufficient detail to inform stakeholders and DOE decision makers regarding a potential path forward. The recommended path forward will inform Fiscal Year 2019 budget formulation, support potential National Environmental Policy Act (NEPA) analyses, and may or may not include capital asset projects.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Pathways to IEC Standards for Heliostat Design Qualification and Site Acceptance in Central Receiver CSP Applications
This paper surveys the existing landscape of standards relevant to heliostats, identifies their gaps, and proposes a path forward to a comprehensive set of heliostat guidelines, technical specifications, and standards under the framework of International Electrotechnical Commission (IEC) TC 117. Gaps in existing guidelines and standards are surveyed using a three-tiered taxonomy: component-level, heliostat-level, and field-level. At each level, the gap analysis is followed by a proposal for a coordinated path forward on the development of standards. At the component level, advances in the understanding of wind loading should inform a technical specification for drives and structures. Reflectors require consolidation of measurement guidelines into existing standards documents. Communications & controls require technical standards to inform their selection and secure implementation. At the heliostat level, IEC 62817 (solar trackers) adequately characterizes drive systems, structures, and electronics, but requires adaptation to heliostats' use patterns, operating modes, and expected life cycles. IEC 62817 does not address heliostat beam quality and pointing accuracy, but the process for determining both is elaborated in the SolarPACES Guideline for Heliostat Performance Testing. This SolarPACES document requires two main modifications: adaptation to IEC language and inclusion of testing after heliostats which have undergone accelerated weathering and mechanical cycling (to understand performance degradation). At the field level, IEC 62862-4-2 addresses the function and control of heliostat fields but does not cover the statistically rigorous testing of heliostat groups, or field performance factors like security and soiling. The addition of documents under IEC-62862-4 is proposed to address this gap.
beam↗
PRP Comments for ICF Q1/Q2 FY17 Experiments 3/10/16
The PRP generally endorsed the Program plan during the short time for discussions. We agree that the strategy to develop a hohlraum that is symmetric and has low laser-plasma instabilities and to develop an alternative method for supporting the capsule is the best path forward for making progress in understanding ignition performance. The Program is oriented toward a milestone in 2020 for “determining the efficacy of NIF for ignition and credible physics-scaling to multi-megajoule yields for all ICF approaches.” We are concerned that the time and resources are not sufficient to vet all of the various approaches that are being pursued to make an informed decision by this date. For NIF to meet this goal, a process will be needed to to select the most promising paths forward. We recommend that the Program develop this process for selecting the path forward to optimize resources. We were glad to see that the direct drive program took our comments under consideration. We think that the proposed experiments have the program headed in a better direction. The PRP had only a short time to discuss the detailed experimental proposals. The following are comments on the detailed proposals. We did not have time to discuss them as a group. They represent individual opinions and provided to you as feedback to your proposals.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Comprehensive Review of DPF-based Flash Neutron Radiography Viability
MJOLNIR (MegaJOule Neutron Imaging Radiography) is a Dense Plasma Focus (DPF) being developed by LLNL as a prototype to assess the viability of a DPF as a flash neutron radiography source. To date, MJOLNIR has discharged up to 1.3 MJ of stored energy into a deuterium plasma load and achieved yields up to 1.2 × 10 12 neutrons per discharge. The MJOLNIR pulse length already meets the preliminary requirements for flash neutron radiography and we demonstrate in this report plausible paths forward to meet the yield requirement in a deuterium plasma. MJOLNIR’s neutron spot size has been characterized to be a factor of two greater than radiography requirements and presents the greatest challenge. A path forward to sufficiently shrinking spot size is outlined in this report, using a combination of gas dopants and a smaller anode implosion radius. A DPF is a plasma device with coaxial electrodes whose discharge ends with a stagnated hot and dense plasma column on-axis, at the tip of the central anode. Inside the MJOLNIR DPF plasma column, both thermal and beam target processes generate neutrons. To understand the underlying physics of neutron generation inside the DPF, we model the experiment using a combination of kinetic, fluid, and reduced-order models we have been developing for over ten years at LLNL. Our numerical tools are also pivotal to charting the path forward because they allow us to numerically test out which modifications would improve the DPF’s characteristic output.
42 ENGINEERING↗
Panel Session 76: US DOE Problematic Waste Streams and Policy Impacts
This panel provided an overview of DOE problematic waste streams including status and path forward. Potential policy implications that exist now and/or in the future were discussed. Topics included, greater-than-Class C low level waste, depleted uranium, and sodium waste. The panel also discussed potential treatment options for these wastes. As part of the introduction, Renee Echols welcomed the audience and went over a quick overview of what would be discussed on the panel. Theresa Kliczewski provided an overview of why this panel is relevant to US Department of Energy's Office of Environmental Management: there are problematic waste streams that still exist across the DOE cleanup complex. Theresa noted that the DOE EM Headquarters Office of Waste and Materials Management (EM-4.2), for which she is employed with, continues to work with the DOE cleanup sites on a path forward for these problematic waste streams. Presentations proposed include: 1 - Overview of Greater-Than-Class C Low-Level Radioactive Waste Disposal Path Forward (Theresa Kliczewski, US DOE EM (USA)); 2 - Status of Draft Supplemental Environmental Impact Statement for Disposition of Depleted Uranium Oxide Conversion Product Generated from DoE's Inventory of Depleted Uranium Hexafluoride (Jaffet Ferrer-Torres, US DOE (USA)); 3 - Problematic Waste Streams on the Oak Ridge Reservation (John Wrapp, UCOR (USA)); 4 - K Basin Sludge Removal (Ryan Covert, CH2M Hill PRC (USA)); 5 - Providing Technology Solutions for Treatment of Challenging Waste Streams (Tammy Monday, Perma-Fix Environmental Services (USA)); 6 - Treatment of Problematic Reactive Metal Waste Using the GeoMelt{sup R} In-Container Vitrification (ICV{sup TM}) Process (Ron Mitchell, Veolia Nuclear Solutions (USA))
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Analysis techniques for background rejection at the MAJORANA DEMONSTRATOR
The MAJORANA Collaboration is constructing the MAJORANA DEMONSTRATOR, an ultra-low background, 40- kg modular HPGe detector array to search for neutrinoless double beta decay in {sup 76}Ge. In view of the next generation of tonne-scale Ge-based 0νβ β-decay searches that will probe the neutrino mass scale in the inverted-hierarchy region, a major goal of the MAJORANA DEMONSTRATOR is to demonstrate a path forward to achieving a background rate at or below 1 count/tonne/year in the 4 keV region of interest around the Q-value at 2039 keV. The background rejection techniques to be applied to the data include cuts based on data reduction, pulse shape analysis, event coincidences, and time correlations. The Point Contact design of the DEMONSTRATOR’s germanium detectors allows for significant reduction of gamma background.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Status of the Majorana Demonstrator
The MAJORANA Collaboration is constructing the MAJORANA DEMONSTRATOR, an ultra-low background, modular, HPGe detector array with a mass of 44-kg (29 kg {sup 76}Ge and 15 kg {sup nat}Ge) to search for neutrinoless double beta decay in {sup 76}Ge. The next generation of tonne-scale Ge-based neutrinoless double beta decay searches will probe the neutrino mass scale in the inverted-hierarchy region. The MAJORANA DEMONSTRATOR is envisioned to demonstrate a path forward to achieve a background rate at or below 1 count/tonne/year in the 4 keV region of interest around the Q-value of 2039 keV. The MAJORANA DEMONSTRATOR follows a modular implementation to be easily scalable to the next generation experiment. First, the prototype module was assembled; it has been continuously taking data from July 2014 to June 2015. Second, Module 1 with more than half of the total enriched detectors and some natural detectors has been assembled and it is being commissioned. Finally, the assembly of Module 2, which will complete MAJORANA DEMONSTRATOR, is already in progress.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
The Majorana low-noise low-background front-end electronics
The Majorana Demonstrator will search for the neutrinoless double beta decay (ββ(0ν)) of the isotope ⁷⁶Ge with a mixed array of enriched and natural germanium detectors. In view of the next generation of tonne-scale germanium-based ββ(0ν)-decay searches, a major goal of the Majorana Demonstrator is to demonstrate a path forward to achieving a background rate at or below 1 cnt/(ROI-t-y) in the 4 keV region of interest (ROI) around the 2039-keV Q-value of the ⁷⁶Ge ββ(0ν)-decay. Such a requirement on the background level significantly constrains the design of the readout electronics, which is further driven by noise and energy resolution performances. We present here the low-noise low-background front-end electronics developed for the low-capacitance p-type point contact (P-PC) germanium detectors of the Majorana Demonstrator. This resistive-feedback front-end, specifically designed to have low mass, is fabricated on a radioassayed fused-silica substrate where the feedback resistor consists of a sputtered thin film of high purity amorphous germanium and the feedback capacitor is based on the capacitance between gold conductive traces.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
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↗
Additive Manufacturing of MITL's and Convolutes
Stockpile stewardship requires accurate and predictive models relying on the generation of extreme environments which is both incredibly difficult and profoundly necessary. Next generation pulsed power facilities (NGPPF), where these environments are created, may require a paradigm shift in equipment engineering/manufacture to fulfill this need. Therefore, this research aims to investigate the limitations, capabilities and efficacy of leveraging advancements in the field of additive manufacturing (AM) in order to produce novel power flow components for NGPPFs. This work focused on commercial 3D metal AM equipment producing several prototypes addressing prescient needs/shortcomings, and a technique wherein a lightweight polymer core is metalized. Ultimately, commercial 3D metal AM is considered a viable path forward but would require a sizeable investment and does not currently support the scale and complexity necessary for NGPPFs. Moreover, initial results from our composite technique are promising and is considered a realizable path forward given further investigation.
42 ENGINEERING↗