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DOE OSTI2019

International Government Collaboration in ISD (In Situ Decommissioning/In Situ Disposal) - 19261

In situ decommissioning (ISD) is considered by IAEA as the permanent entombment of a legacy facility in 'a structurally long lived material' (e.g. concrete) and is considered a solution only under 'exceptional circumstances' (e.g. following a severe accident). However, this definition of ISD as 'only' entombment is not universally accepted; the approach has been implemented as a decommissioning approach by the US Dept of Energy in the past decade at the Savannah River Site (P and R reactors)2,3, the Hanford site (U Canyon) and at the Idaho site (CP601, CP640 and CP633). The application of ISD outside of the United States has been much less common for large facilities although its use for underground substructures (e.g. discarded pipelines) is commonplace. Proponents of ISD consider it beneficial since it eliminates the need to remove, package and transport contaminated equipment from a nuclear legacy site to a disposal facility and it maximizes the use of an existing nuclear site footprint by consolidating equipment in one place. ISD is considered to offer major safety benefits to both workers and the public, as well as major cost and schedule benefits to Government. Opponents of the approach cite the fact that, following ISD, the decommissioned facility has effectively become a long-term waste disposal site and that regulations pertaining to long term waste disposal have been circumvented. Given the increasing pressure on environmental cleanup budgets and schedules around the world, countries such as the United Kingdom, Canada and Japan are considering ISD in its various forms as a potential path forward for decommissioning certain facilities in lieu of the more traditional approaches of either deferred decommissioning or immediate decontamination/demolition. To address this emerging area of decommissioning, a Governmental Technical Information Exchange meeting was held in December 2017 at the DOE Savannah River Site in Aiken, SC, to bring together responsible parties from the US Dept of Energy (DOE), Atomic Energy of Canada Ltd (AECL), the UK Nuclear Decommissioning Authority (NDA) and the Japanese Atomic Energy Agency (JAEA) and those countries' respective regulatory agencies to share information about respective 'best practices' and challenges with ISD. Representatives from organizations such as IAEA and US Nuclear Regulatory Commission (US NRC) also participated to discuss their organizations' perspectives and position on ISD. Following the meeting, a series of Working Groups were established which have continued the dialogue in three key areas 5; - ISD-Defined: Identify and share case-specific ISD solutions which allows for the full spectrum of needs and which demonstrate that 'entombment' is not the only definition of 'ISD'. - Regulatory - Share and discuss regulatory concerns and challenges with ISD; - Benchmarking - Share information to support informed and transparent decision-making in ISD. This paper discusses the plans for ISD in some of the countries involved in the December meeting and provides an update on the topics being discussed, and progress being made, by the Working Groups that were formed at the meeting. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2021

Molten Salt Reactor Sourdough Refueling and Waste Management Strategy

This paper presents a new approach to the spent nuclear fuel (SNF) problem, which is uniquely enabled by a liquid fuel form, specifically as in the case of molten salt reactor (MSR) systems. Managing the SNF problem is critical for public acceptance of nuclear power as a climate change solution. An MSR can be refueled while operating by adding more fresh fuel salt, which grows the in-core fuel salt volume. This growth will eventually double the size of the original fuel salt, allowing to start another core with this excess fuel so long as the daughter reactor is of the same design and there is sufficient excess fuel. This study explores how such a “sourdough” strategy would work in MSRs and provides an initial calculation methodology to find the correct refueling rates to match the desired growth curve of power generation. Higher uranium enrichment levels of the refuel salt result in lower refueling rates and thus a longer doubling time. As a result, the refuel salt uranium enrichment can be tailored to match a postulated clean power generation capacity expansion. This approach allows postponing the spent nuclear fuel disposal issue using the sourdough method. Along with the MSR fuel’s unique properties, it suggests a new path towards managing nuclear waste until long-term solutions become economically viable.

Wheeler, Alexander M.↗

DOE OSTI2019

Development of Waste Inventory for Probabilistic Performance Assessment Modeling - 19361

Estimation of radioactive waste inventory is a key initial step in the development of an environmental fate and transport model for performance assessment (PA) of radioactive waste sites. PA model output is often sensitive to parameters that represent inventory as a source term, yet estimation is a difficult problem. Inventory estimation for a probabilistic performance assessment (PPA) is related to, but distinct from, that performed for waste excavation, characterization, and offsite disposal. The latter appropriately focuses on obtaining the most detailed information possible on specific hazards and locations; however, these questions cannot be fully answered without intrusive site characterization efforts. This type of characterization is often not feasible when assembling information regarding a source term in a PPA model. Development of waste inventory for a PPA is one piece of a larger hierarchical model. The physical process model represented by Goldsim computer code represents one level of the hierarchy, and the second level of the hierarchy involves estimation of inputs such as inventory, transport, and risk parameters. The estimation of inputs is not a straightforward problem. The parameters of a computer model often do not have an equivalence to the physical quantities they describe, and estimation of the physical quantities themselves can be difficult due to limitations of available information. Inventory information for the West Valley Site in upstate New York is based on data from historical shipping and disposal forms. In the 1990's, the West Valley Demonstration Project (WVDP) compiled information from existing databases and historical waste records into one complete modern database. A conceptual model was then applied and used with recorded information to characterize the waste mass and radionuclide composition for each waste burial. Information was ultimately aggregated over all waste records to estimate the mass of each radionuclide within each trench, hole, or caisson. Three decades later, we revisit the master database, make updates with newly-identified information, and incorporate the conceptual model previously used for inventory estimation in the hierarchical modeling framework. We characterize uncertainty using probability distributions for waste mass and radionuclide composition at the individual shipment or individual burial level. Uncertainty incorporated at the lowest level of the hierarchy is ultimately carried through to uncertainty in PPA model endpoints. Sensitivity analysis of early model results is then applied to identify influential inputs and guide subsequent efforts towards parameters that drive risk. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2019

Magnetic Nanoparticles Impregnated, Cross-Linked, Porous Chitosan Microspheres for Efficient Adsorption of Methylene Blue from Pharmaceutical Waste Water

The study demonstrates the preparation of MnFe{sub 2}O{sub 4} impregnated chitosan-microspheres (CMMS) as adsorbents for efficient removal of cationic thiazine dye, methylene blue. A facile approach with great economic and technical advantages to obtain highly crystalline manganese ferrite nanoparticles by solution combustion method is accounted. CMMS were characterized and evaluated for MB adsorption using linear forms of Freundlich and Langmuir adsorption isotherms, pseudo-first order, pseudo-second order and Elovich kinetic models. Application of CMMS to pharmaceutical waste, desorption of MB and reusability of CMMS are reported. Significantly, MB concentration in treated real sample was reduced by ~ 18 times to that of initial concentration. Graphic Abstract: .

36 MATERIALS SCIENCE↗

DOE OSTI2012

Advancing Performance Assessment for Disposal of Depleted Uranium at Clive Utah - 12493

A Performance Assessment (PA) for disposal of depleted uranium (DU) waste has recently been completed for a potential disposal facility at Clive in northwestern Utah. For the purposes of this PA, 'DU waste' includes uranium oxides of all naturally-occurring isotopes, though depleted in U-235, varying quantities of other radionuclides introduced to the uranium enrichment process in the form of used nuclear reactor fuel (reactor returns), and decay products of all of these radionuclides. The PA will be used by the State of Utah to inform an approval decision for disposal of DU waste at the facility, and will be available to federal regulators as they revisit rulemaking for the disposal of DU. The specific performance objectives of the Clive DU PA relate to annual individual radiation dose within a 10,000-year performance period, groundwater concentrations of specific radionuclides within a 500-year compliance period, and site stability in the longer term. Fate and transport processes that underlie the PA model include radioactive decay and ingrowth, diffusion in gaseous and water phases, water advection in unsaturated and saturated zones, transport caused by plant and animal activity, cover naturalization, natural and anthropogenic erosion, and air dispersion. Fate and transport models were used to support the dose assessment and the evaluation of groundwater concentrations. Exposure assessment was based on site-specific scenarios, since the traditional human exposure scenarios suggested by DOE and NRC guidance are unrealistic for this site. Because the U-238 in DU waste reaches peak radioactivity (secular equilibrium) after 2 million years (My) following its separation, the PA must also evaluate the impact of climate change cycles, including the return of pluvial lakes such as Lake Bonneville. The first draft of the PA has been submitted to the State of Utah for review. The results of this preliminary analysis indicate that doses are very low for the site-specific receptors for the 10,000-year compliance period. This is primarily because DU waste is not highly radioactive within this time frame, the DU waste is assumed to be buried beneath zones exposed by erosion, groundwater concentrations of DU waste constituents do not exceed groundwater protection limits with in the 500-year compliance period, and the first deep lake occurrence will disperse DU waste across a large area, and will ultimately be covered by lake-derived sediment. A probabilistic PA model was constructed that considered DU waste and decay product doses to site-specific receptors for a 10,000-yr performance period, as well as deep-time effects. The quantitative results are summarized in Table VII. Doses (as TEDE) are always less than 5 mSv in a year, and doses to the offsite receptors are always much less than 0.25 mSv in a year. Groundwater concentrations of Tc-99 are always less than its GWPL except when the Tc-99 contaminated waste is disposed below grade. Even in this case, the median groundwater concentration is only 4.18 Bq/L (113 pCi/L), which is more than one order of magnitude less than the GWPL for Tc-99. The results overall suggest that there are disposal configurations that can be used to dispose of the proposed quantities of DU waste that are adequately protective of human health. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2019

Bioaugmentation of an Engineered Metal Treatment Wetland with Cupriavidus SRS

There are many chemical methods to remediate copper (Cu) from the environment. However, the use of microorganisms has been identified to be cheaper and more efficient in remediating toxic compounds in a method known as bioremediation. A microorganism, Cupriavidus SRS, is a metal resistant, rod shaped, gram negative bacteria that was isolated from a location with heavy metal contamination. As a predator this isolate has the ability to attack gram-negative and gram-positive bacteria. It is highly tolerant to Cu, and the isolates growth initiation is stimulated by Cu. Wang et al. (2015) determined that efflux pump activity is one of the most important mechanisms of heavy metal tolerance and the Cupriavidus genus demonstrates this behavior. In this study, Cupriavidus SRS will be inoculated to sediment and water from an area with high concentrations of Cu and zinc, to determine the ability of the isolate to grow and survive in a high level Cu wetland as well as the bioremoval efficiency. The H-02 wetland in the AL1 outfall area is an engineered wetland that was constructed to utilize natural processes associated with sediments and microbial communities to remove contaminants from waste waters at the Savannah River Site. Specifically, this wetland treats the building processes and runoff form the Tritium Processing Facility in H-area to prevent Cu and Zn from entering the water before the contaminants go in the Savannah River. Distributions of Cu and Zn follow organic matter levels with higher densities along the shoreline showing that metal concentrations correlate with organic matter content. Cupriavidus SRS Growth: Cupriavidus SRS was isolated at the Savannah River Site from an area with heavy metal contamination. Cultures were grown in R2A medium at 25 deg. C and shaken at 80 rpm for liquid cultures for 5 days. Sediment and Water Collection: All samples were collected from the AL1 Outfall area within the Department of Energy's Savannah River Site. Sediment cores, organic layer samples, and water samples were collected from the Inlet and Outlet cells in triplicate. Only water samples were collected from the basin. Cell Pellet: After centrifugation at 10,000 RPM for 10 minutes the supernatant was removed. 1 mL of phosphate buffer saline was added to the tube, vortexed, and recentrifuged. Inoculation of Sediment and Water: All samples were done in triplicate, vortexed after inoculation, and put on the shaker for 72 hours. Day 0 begins when the samples are removed from the shaker. Experimental Set-Up: All samples were done in triplicate. All sediment samples were centrifuged at 7500 RPM for 10 minutes on Day 0 and Day 5. All the sediment and water samples were filtered with a 0.2 μm nylon filters to obtain approximately 10 mL of supernatant on Day 0 and Day 3. pH was taken 24, 48, and 72 hours after the samples had been on the shaker. Plate Count: Plate counts were done on Day 0 and Day 3 to determine Cupriavidus SRS growth following a quantitative counting method from Seely et al. (1972). This project is ongoing and the goal is to determine if Cupriavidus SRS has the ability to uptake excess Cu out of the environment. These could be some possible results for the experiment: - The isolate uptakes too much Cu, dies, and releases Cu back into the environment. - The isolate is able to uptake Cu, continue to live, but chemically changes the environment introducing new problems. - The isolate is able to uptake Cu, continue to live, and does not disrupt the environment with toxic chemical changes.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2015

Nepheline crystallization in boron-rich alumino-silicate glasses as investigated by multi-nuclear NMR, Raman, & Mössbauer spectroscopies

Not Available

McCloy, John (ORCID:0000000174767771)↗

DOE OSTI2014

Performance Monitoring of Residential Hot Water Distribution Systems

Current water distribution systems are designed such that users need to run the water for some time to achieve the desired temperature, wasting energy and water in the process. We developed a wireless sensor network for large-scale, long time-series monitoring of residential water end use. Our system consists of flow meters connected to wireless motes transmitting data to a central manager mote, which in turn posts data to our server via the internet. This project also demonstrates a reliable and flexible data collection system that could be configured for various other forms of end use metering in buildings. The purpose of this study was to determine water and energy use and waste in hot water distribution systems in California residences. We installed meters at every end use point and the water heater in 20 homes and collected 1s flow and temperature data over an 8 month period. For a typical shower and dishwasher events, approximately half the energy is wasted. This relatively low efficiency highlights the importance of further examining the energy and water waste in hot water distribution systems.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

DOE OSTI2017

A Comparison of Social and Economic Engagement Approaches: Lessons from Recent International Radioactive Waste Projects - 17478

The central challenge of any proposed radioactive waste management project is securing not only regulatory permissions, but also a social license to operate. 'Social license' generally refers to a community's acceptance or approval of a specific project. Oftentimes development of social license occurs outside of, or in parallel to, formal regulatory or permitting processes, and requires sustained commitment and proposed economic benefits to communities by proponents to acquire, build, and sustain social capital in the context of trust-based relationships. Historically, radioactive waste management projects have defaulted to demagoguery and 'siege warfare' modes of thinking and action by both proponents and opponents. While radioactive waste management projects are always inherently controversial, it is only recently that project owners and developers have experimented with alternative forms of social engagement outside of, or in addition to, formal regulatory processes. This paper compares and contrasts recent projects in Canada, Australia, the United Kingdom, and the United States, by examining distinct approaches to social engagement, with a focus on new methods that have been used to promote mutual understanding, foster rational debate, build confidence, promote economic development, and secure social license. The projects examined span the life-cycle of radioactive waste management development, from ones that are purely aspirational, to ones in early planning stages, to ones seeking a host community, to one that is focused on sustainment of existing social license. Several notable lessons and innovative practices are identified that will be of interest to radioactive waste management project owners and developers, non-governmental organizations, potential host communities, and political decision-makers for such projects. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2022

Glass Crystallization Constraints for WTP LAW Operations: Assessment of Isothermal Treatments on Crystal Formation

Much work has been done to expand the glass composition region available for operation of the Hanford Tank Waste Treatment and Immobilization Plant. This includes the development of updated glass property-composition models as well as constraints. This report supports this effort by suggesting constraints for avoiding excessive, and likely detrimental, crystallization during melter operation while processing advanced low-activity glasses. The constraints target Cassiterite and ZrO 2 -containing phases (ZCP, e.g., Baddeleyite and Zircon) that can form when melter temperatures drop below 1100 °C. These types of crystals were found to be potentially detrimental during processing as they are denser than low-activity waste glass melts; with densities of 6.95 g/cm 3 for Cassiterite and 5.68 g/cm 3 for Baddeleyite (the most prevalent ZCP). Compared to melt densities of approximately 2.65 g/cm 3 . Thus, they have the potential to form during melter idling and settle to the bottom of the melter or inside the melter. If the crystals are present in appreciable amounts, they can result in blockages of the pour-spout riser, which impacts glass pouring and melter operation. Additionally, SnO 2 and ZrO 2 are added to glass formulations to improve glass durability. Their precipitation from the melt may reduce overall glass durability. Using previously acquired results and results from testing during this effort, the following constraints (Table S.1) were determined and are recommended to reduce the risk of forming crystals of the types and concentrations that are likely detrimental to melter operation.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2019

Fine Calcium Carbonate Production by CO2 Mineralization of Industrial Waste Brines

Calcium carbonate production via CO2 mineralization offers an attractive route for carbon capture and utilization. The process sequesters CO2 in a stable form of fine precipitated calcium carbonate, a high-value product with unit price in the range of $230-$280/t and a global market projected to reach 99 M tons in 2020. However, two critical barriers hinders CO2 mineralization—(i) the need for costly processes such as electrolysis or addition of alkali hydroxides to maintain alkalinity during mineralization, and (ii) the geographic location mismatch between Ca-rich solutions (or brines) CO2 generation sources (e.g. power plants) which often renders efficient integration of feedstocks impractical. To simultaneously address these challenges, a new process is developed to integrate CO2 mineralization-based carbonate production into the zero liquid discharge water (ZLD) treatment systems at coal-fired power plants. In this process, Ca-rich streams, such as produced water from oil and gas extraction or carbon storage operations, serves as the Ca-source. An H+/Na+ ion-exchange cycle is designed to provision alkalinity during mineralization and regenerate the ion-exchange reagent in solutions with high salinity. Ca-depleted streams are then treated within a centralized ZLD system. The process beneficially utilizes reject streams that are available at substantial quantities in the vicinity of coal power plants within several U.S regions. In addition, the process utilizes post-desulfurization flue gas from coal-fired power plants as is. The CO2 conversion reactions are performed in alkaline streams at ambient pressure, thereby minimizing the energy burden. By beneficiation of industrial waste streams with low energy input, this process offers significant technical advantages in energy and CO2 footprint over the current paradigm of precipitated calcium carbonate production. Overall, the new process provides a unique route to integrate CO2 emissions control and wastewater treatment for coal power plants, while producing high-value product to offset the economic burden associated with waste management.

Simonetti, Dante↗

DOE OSTI2019

Fine Calcium Carbonate Production by CO2 Mineralization of Industrial Waste Brines

Simonetti, Dante↗

DOE OSTI2018

Effects of Blending and In-Tank Pretreatment on Direct Feed Hanford High Level Waste Vitrification - 18434

A direct feed high level waste (DFHLW) option is under consideration for early operations of the Hanford Tank Waste Treatment and Immobilization Plant (WTP). In this option, the Pretreatment Facility would be bypassed in order to support an earlier start-up of the HLW Vitrification Facility. For HLW, this would mean that ultrafiltration and caustic leaching that would otherwise have been performed either would not be performed or would be replaced by interim pretreatment functions such as in-tank washings. These changes could result in higher aluminum contents, higher chromium contents, higher fractions of supernate, and lower solids contents in the HLW feed. As a result, glass formulations and downstream vitrification operations will be impacted. In the present work, we investigate the effects of various waste blending and in-tank pretreatment scenarios on DFHLW glass waste loadings, canister counts, and processing rates. Eleven source tanks and five waste groups were selected for the studies of waste blending. In addition, the five waste groups selected were the subjects of an in-tank pretreatment study. Glass property-composition models and melter test data were used to calculate waste loadings, canister counts, processing rates, and treatment durations for a range of DFHLW scenarios. The processing scenarios were defined by the types of waste blending and in-tank pretreatment that were assumed. Blending cases were evaluated that ranged between the 'No Blend' and 'Total Blend' extremes and included pairwise blending (blending of two source tanks, either completely or in various proportions) and macro-batches formed from various combinations of the source tanks. Over 36,000 possible pairwise blending scenarios were evaluated and an optimal retrieval/blending sequence was identified. The waste loading of this optimal sequence is within 0.03 wt% of the 'Total Blend' case. Further, a total of 38 retrieval sequences were identified that have waste loadings within 0.1 wt% of the 'Total Blend' case. To evaluate the effects of in-tank pretreatment, an in-tank wash/settle/decant process was assumed and tank-specific wash factors were employed. Washing of the macro-batch blends gave a general increase in HLW loading, decrease in canister count, and decrease in glass yield. Glass yields are towards the low end of the values expected for the WTP, which could lead to lower than nominal glass production rates. The waste loading increases and canister count reductions with washing were small for two of the wastes indicating that direct treatment of the unwashed waste may be practical. For wastes that are relatively low in sulfate and halides, excessive washing is counterproductive. The results highlight the importance of maintaining high solids content in the HLW feed to maintain glass production rates. The results also illustrate that the optimum washing strategy will need to be evaluated on a tank-to-tank basis. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

NASA NTRS1993

Converting environmental wastes into valuable resources

This concept employs a viable energy saving method that uses a solvent to separate oil from particle matter; it can be used in metal forming industries to deoil sludges, oxides, and particle matter that is presently committed to landfill. If oily particles are used in their oily state, severe consequences to environmental control systems such as explosions or filter blinding, occur in the air handling equipment. This is due to the presence of hydrocarbons in the stack gasses resulting from the oily particles. After deoiling, the particles can be recycled and the separated oil can be used as a fuel. The process does not produce a waste of it's own and does not harm air or water. It demonstrates the dual benefits of it being commercially viable and in the national interest of conserving resources.

Duval, Leonard A.↗

DOE OSTI2019

Mercury Speciation and Quantification of Hanford 241-AP-107 Tank Waste Feed and Treated Samples

This report describes the second phase of a multi year project to adapt and develop an analytical technique for the low-level determination of total mercury (HgT), elemental mercury (Hg0), and monomethyl mercury (MeHg, hereafter referred to as methyl mercury) in Hanford tank waste. The focus of Phase II was to quantify the mercury (Hg) species total, elemental, and methyl mercury from a raw sample and treated (i.e., filtered and cesium-decontaminated) waste samples originating from Hanford waste tank 241-AP 107. The focus of Phase I work was to determine if mercury species can be preconcentrated from aqueous Hanford tank waste solution onto a solid adsorbent while simultaneously eliminating or very significantly reducing the parent radionuclide activity. This was demonstrated by developing protocols for the preparation, separation, and collection of total mercury and methyl mercury onto solid adsorbents, then measuring the adsorbents for radiological content at Pacific Northwest National Laboratory’s (PNNL’s) Radiochemical Processing Laboratory (RPL) on the Hanford Site. During Phase II, the Hanford tank waste material was preserved, separated (through distillation or digestion), then collected as either solid adsorbents or into liquid distillate form at the RPL and transferred to the PNNL Marine Sciences Laboratory (MSL) in Sequim, Washington, for analysis and quantification. Quantification of total, elemental, and methyl mercury was conducted under radiological control at the MSL using the ultra trace analytical capabilities available there.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2020

Carbon Fiber Prepreg Recycling- Automated Perform Manufacturing Equipment (Final Technical Report)

Discontinuous fiber composites have a compelling business case as related to light metals such as aluminum and magnesium machined or die cast components. DFC’s have been in commercial production using carbon fiber/epoxy prepreg for both commercial aircraft and for military applications for a number of years and their usage is expanding into automotive and consumer goods components. Reasons for this include significantly lower cost as compared to continuous fiber composites easier design and understanding of the material by metal traditionalists, higher degree of part complexity with relatively simple and low cost molds when compared to high-pressure die casting, and potential for near zero waste. IACMI’s 10-year goals of reduction in carbon fiber reinforced plastics manufacturing cost by 25%, reduction in their embodied energy by 50%, and recyclability of 95% can all be advanced through robust recycling. With recycling We have shown that a 15% contribution in manufacturing cost reduction is feasible, that a significant reduction in embodied energy (over 90% for the recycled fraction) is achievable, and that when combined with primary pyrolysis recycling, the 95% target can be met. Large-scale application of advanced composites began with the aerospace industry, and CRTC’s location in Washington State provided access to a waste stream of nearly 900 tonnes/year that was going to landfill. As the aerospace industry has automated parts production, their material forms have become significantly easier to recycle, and some evidence of this exists for the future automotive and wind turbine components as well. CRTC decided to focus on re-purposing the carbon fiber/epoxy aerospace scrap streams through materials reformatting and reuse, and not on primary recycling (pyrolysis mainly) as this technology is commercially available. The main reasons for this were that it offers a route to effective use of the most widely available and consistent feedstock called edge-trim, as well as allows creation of complex and low-cost parts using rapid and cost-effective compression molding technologies. The reasons also include leading the way for potential automotive pre-preg recycling as the combination of roughly 85% virgin pre-preg and 15% recycled pre-preg directly supports IACMI’s goals and enables significant part cost reduction and a path to zero-waste composite manufacturing at the OEMs or Tier 1’s. The purpose of the project was to develop equipment and technology to transform continuous fiber pre-preg in roll forms into smaller chip-format DFC feedstock, and to determine impacts on moldability and performance based on lessons learned along the path. The availability of scrap from pre-preg manufacturers was a significant value to the program even though the aerospace pre-preg is designed to be autoclave molded thus has handling, tackiness, and processing factors that are not ideal for DFCs. The scope of the project was to develop a Phase 1 system that could identify and resolve some of the major hurdles, determine where to focus effort on building a commercial-scale Phase 2 system, and develop technology for handling a wide variety of incoming scrap materials to produce the most usable product. A chopping system was developed and reduced to practice via an experimental approach that enabled all forms of scrap coming from the pre-preg manufacturers and some forms of the scrap coming from OEM production lines to be very effectively re-purposed. The systems that were developed were not considered to be production robust but rather identified and resolved some of the major technical hurdles, and demonstrated the path towards effective full-scale commercialization.

36 MATERIALS SCIENCE↗

DOE OSTI2015

Effect of the Form of Iron on HLW Melt Rate

The primary objective of the work reported herein was to determine the effect of the form of iron in the HLW stream on feed processing rate. Secondary objectives were to determine the effect of iron form on feed properties, glass properties, and carryover from the melter during vitrification. This was accomplished by replacing the Fe(OH) 3 used in a previously tested simulant for C-106/AY-102 actual waste with either goethite (FeO(OH)), hematite (Fe 2 O 3 ), magnetite (Fe 3 O 4 ), or a mixture of iron oxides, and processing the resulting melter feeds on the DM100 melter system. Glass forming additives were combined with the high iron simulant to produce melter feed targeting the HLW-NG-Fe2 glass composition. Melter feed samples also underwent testing for rheological properties and processing rate using a VGF system.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2022

Effect of network connectivity on behavior of synthetic Broborg hillfort glasses

There is wide industrial interest in developing robust models of long-term (>100 years) glass durability. Archeological glass analogs, glasses of similar composition, and alteration conditions to those being tested for durability can be used to evaluate and inform such models. Two such analog glasses from a 1500-year-old vitrified hillfort near Uppsala, Sweden have previously been identified as potential analogs for low concentration Fe-bearing aluminosilicate nuclear waste glasses. However, open questions remain regarding the melting environment from which these historic glasses were formed and the effect of these conditions on their chemical durability. A key factor to answering the previous melting and durability questions is the redox state of Fe in the starting and final materials. Past work has shown that the melting conditions of a glass-forming melt may influence the redox ratio value (Fe +3 /ΣFe), a measure of a glass's redox state, and both melting conditions and the redox ratio may influence the glass alteration behavior. Synthetic analogs of the hillfort glasses have been produced using either fully oxidized or reduced Fe precursors to address this question. In this study, the melting behavior, glass transition temperature, oxidation state, network structure, and chemical durability of these synthesized glass analogs is presented. Resulting data suggests that the degree of network connectivity as impacted by the oxidation state of iron impacted the behavior of the glass-forming melt but in this case does not affect the chemical durability of the final glass. Glasses with a lower degree of melt connectivity were found to have a lower viscosity, resulting in a lower glass transition temperature and softening temperature, as well as in a lower temperature of foam onset and temperature of foam maximum. This lower degree of network connectivity most likely played a more significant role in accelerating the conversion of batch chemicals into glass than the presence of water vapor in the furnace's atmosphere. Future work will focus on using the results from this work with outcomes from other aspects of this project to evaluate long-term glass alteration models.

36 MATERIALS SCIENCE↗