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At least 1,423 records · Page 79

Development of a High Temperature Microbial Fermentation Processfor Butanol Production

Transforming renewable biomass into cost competitive high-performance biofuels and bioproducts is key to US energy security. Butanol production by microbial fermentation and chemical conversion to polyolefins, elastomers, drop-in jet or diesel fuel, and other chemicals is a promising solution. A high temperature fermentation process can facilitate butanol recovery up to 40%, by using gas stripping. Other benefits of fermentation at high temperatures are optimal hydrolysis rates in the saccharification of biomass which leads to maximized butanol production, decrease in energy costs associated with reactor cooling and capital cost associated with reactor design, and a decrease in contamination and cost for maintaining a sterile environment. Butanol stripping at elevated temperatures gives higher butanol production through constant removal and continuous fermentation. We describe methods used in an attempt to genetically prepare Geobacillus caldoxylosiliticus for insertion of a butanol pathway. Methods used were electroporation of electrocompetent cells, ternary conjugation with E. coli, and protoplast fusion.

09 BIOMASS FUELS↗

Evaluation of ALSEPO

The level three milestone (M3FT-17IN030102013) "Evaluation of ALSEPO” has been completed. Researchers at INL are studying the impacts of gamma radiolysis on the Actinide Lanthanide Separation Process (ALSEP) flowsheet. The ALSEP process is being developed by the DOE-NE Material Recovery and Waste Form Development Campaign. The process solvent used a combination of the solvating extractant N,N,N’,N’-tetra(2-ethylhexyl)diglycolamide and the cation exchanging extractant 2-ethylhexylphosphonic acid mono-2-ethylehxyl ester dissolved in an aliphatic diluent. The actinides and lanthanides are co-extracted from nitric acid solution and the actinides are selectively stripped using a carboxylic acid buffered aminopolycarboxylic acid solution. The results irradiation studies previously performed at the INL on another diglycolamide-based solvent extraction system containing 1-octanol as a phase modifier suggested that the octanol may be serving to inhibit the radiolytic degradation of the ALSEP extractants. Although the mechanism of this radioprotection was not determined, the addition of octanol to the ALSEP solvent was proposed. The goal of this research program was to establish the mechanism responsible for the observed increase in the radiation hardiness of the ALSEP solvent upon the addition of 1-octanol. In addition, other possible enhancements of solvent behavior such as possible increased resistance to third phase formation and enhanced extraction/stripping kinetics were examined. The addition of 1-octanol to the ALSEP formulation at either 1 % or 5 % (v/v) does reduce the rate of degradation of the solvent when exposed to gamma radiation. Unfortunately, the addition of the polar phase modifier essentially destroyed the An/Ln separation usually achievable with ALSEP chemistry. This loss of An/Ln separation ability is presumably do to the disruption of HEH[EHP] dimer formation due to the addition of the polar alcohol. The addition of octanol does not appear to have any significant impact upon the rate of removal of either americium or europium radiotracer from the loaded organic solvents. Based upon the distribution ratio data obtained for the 1% octanol and 5 % octanol ALSEPO solvent systems and the lack of any enhancement in the rate of stripping of the actinides and lanthanides from the loaded solvent, further efforts to reformulate the ALSEPO solvent were abandoned.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

Creep Analysis of Poly(ester urethane) Copolymer by Dynamic Mechanical Analysis (DMA): Melt Determination

An experiment is presented utilizing film tension, creep test dynamic mechanical analysis (DMA) to characterize the physical properties of a poly(ester urethane) block copolymer, Estane ® 5703. The polymer was pressed into a sheet from pellet form and cut into strips for analysis utilizing the TA Q800 DMA with film tension clamp. The strips were tested under five constant stress analyses from 0.125 to 0.625, at 0.125 MPa increments. Each analysis was run stepwise through a temperature gradient from 25 °C to 67 .5 °C with 2.5 °C increments, the material reached the instrument maximum displacement at different temperature steps dependent on the constant applied stress. At each of the 18 temperature steps the material was held at constant stress for 10 minutes and allowed to recover under stress-less conditions for 20 minutes. With data analysis recoverable strain data was produced and ultimately a curve of Modulus at temperature, the regression extrapolated to modulus = 0 M Pa. The extrapolated point correlated with data the weighted average melt point of the polymer measured by MDSC, within the regressive least squares fit of the measured moduli. Thereby measuring the melt temperature of a polymer by DMA. This is the third in a series of three reports 4,5 on the physical properties and degradation processes of materials used in polymer bonded explosive 9501 written for submission to the University of Oregon, Masters Industrial Internship Program.

36 MATERIALS SCIENCE↗

Bench Scale Study of Coating Formulations for Abatement of Mercury Vapor and Recovery of Mercury Spills

A sealant formulation has been developed that effectively mitigates human exposure to elemental mercury vapor evolving from spilled mercury. The sealant may be dispensed using a fogging methodology (for industrial settings) or a common spray bottle (for home or school settings). In parallel, the potential for Hg recovery using strippable coatings was evaluated. Four liquid coatings were evaluated: one fogging fixative (FX2) developed at INL for the containment of surface and airborne contamination and three commercially available strippable decontamination gels (Carboset 441, Encor 449, and Stripcoat TLC Free). Bench scale mercury vapor abatement tests were conducted in an enclosure using FX2 with the addition of a mercury absorbent and a mercury reactant. Testing with FX2 showed the reactant contributed significantly to reducing the rate of mercury evaporation. The reactant had a minimal impact on the mercury evaporation rate for the strippable coatings. The potential of strippable coatings to remove/recover mercury was inferred from the adhesive and cohesive performance of sprayable dilutions of the coatings applied to porous and non-porous surfaces. Testing provided the following results: • Mercury vapor concentration was reduced by a factor of 40 using the reactant enhanced FX2 solution, as well as with dilutions of Carboset and Encor. Dilute Stripcoat was less effective at reducing Hg evaporation. • A 100× reduction in Hg evaporation rate was achieved using a coating of FX + the Hg reactant (a.k.a. FX Hg), compared to uncoated Hg. • A 2× reduction in the Hg vapor accumulation rate was achieved using FX Hg, compared to the strippable coatings. • Strippability and adhesion tests show that dilutions of Carboset and Stripcoat can be stripped from a variety of indoor surfaces. Dilute Encor was not strippable. Results suggest FX Hg and dilute Carboset will likely reduce Hg vapor concentrations, in an indoor setting, to a level at or below the Occupational Safety and Health Administration 8-hour human exposure limit (0.1 mg/m3). FX Hg dispensed via fogging would increase worker safety during remediation and demolition of industrial facilities with high levels of elemental mercury contamination. When applied via spray bottle, FX Hg may provide a safe and convenient method for the mitigation of Hg vapor in residential or commercial settings (e.g., offices, homes, schools). This approach would be most beneficial where recovery of the spilled Hg is impractical. A sprayed then stripped application of dilute Carboset may provide a safe and convenient method for recovery of small Hg spills in residential and commercial settings. Further testing is required to determine if liquid Hg sufficiently adheres to the strippable coating to be recovered in this way. If it can be dispensed as a fog, dilute Carboset could be employed to recover Hg contamination in industrial settings. Testing of the foggability of dilute Carboset is required to assess this potential.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Radiation Chemistry of the Hydrophilic DGAs

Short chain diglycolamides (DGAs) are water soluble, and have been used as aqueous stripping and hold back agents in both European and American fuel cycle solvent extraction proposals. An understanding of the influence of radiation on these ligands is critical to the development and implementation of robust separation processes. Therefore, the rates of degradation under radiolysis were measured for four hydrophilic DGAs and compared to the organic-soluble DGAs. Water soluble DGAs were degraded at a faster rate than lipophilic DGAs, but were more stable with increasing molecular weight. The degradation products of the tetraethyldiglycolamide (TEDGA) were also identified and found to be analogous to those produced for lipophilic DGAs in irradiated alkanes. It was concluded that similar products are obtained since reactions in both diluents are by oxidation followed rupture of the weak ether linkage. The fast rate constants of the reactions of two hydrophilic DGAs with the oxidizing •OH radical product of water radiolysis are also shown. Since water-soluble DGAs have been proposed for use as stripping or holdback agents in both European and American fuel cycle scenarios this work was performed in collaboration with colleagues at Forschungszentrum Jülich (FZJ).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Stripper foil considerations for PIP-II to Mu2e-II

The PIP-II linac produces 800 MeV H - beam. The Mu2eII production target is immersed in a high B-field, which would strip H - ions. Thus it is desired to strip the H- ions before they reach the mu2e facility. We discuss design considerations for the stripper foil and its location, foil heating and related extinction design issues.

43 PARTICLE ACCELERATORS↗

Characterization of Creep-Fatigue Crack Growth in Alloy 709 and Prediction of Service Lives in Nuclear Reactor Components (Final Report)

This final report summarizes the activities and results that were obtained by the research team working on the project “Characterization of Creep-Fatigue Crack Growth in Alloy 709 and Prediction of Service Lives in Nuclear Reactor Components”, DOE-NEUP Project 15-8623. This project was mainly concerned with the creep-fatigue crack growth characterization of austenitic stainless-steel Fe-20Cr-25Ni (Alloy 709). For this purpose, an array of experimental and computational activities was performed. The main goal of these activities was to describe and predict the crack growth behavior in Alloy 709 under different conditions of applied loading and temperature. Alloy 709 specimens were tested to describe both the uniaxial creep behavior and creep-fatigue crack growth rates at temperatures between 550°C and 700°C. Microstructure and fracture surface analysis was performed using several experimental techniques, and the defining features of crack growth propagation were identified and described. Thermodynamic and diffusion simulations were performed to understand the microstructure evolution of Alloy 709 at elevated temperatures, and to establish an aging schedule relevant for in-service conditions over extended periods. Experimental testing was performed on both as-received and aged Alloy 709 specimens. Two computational methods were developed to predict crack growth rates and remaining lives in specimens loaded under either fatigue of creep-fatigue. The first computational technique was the finite element method, while the second was strip-yield modeling. Both methods relied on the prediction of crack growth rates using the concept of plasticity-induced crack closure. Crack-tip opening loads were computed and used to perform crack growth rate predictions. The computational predictions matched well with the experimental results. The strip-yield model was shown to be an excellent predictive tool not only for crack growth in austenitic SS Alloy 709, but also in 316 SS, martensitic Cr-Mo steels, Ni-based alloys and Al-based alloys. The main conclusion of this study is that Alloy 709 exhibits excellent creep crack growth resistance at temperatures between 550°C and 700°C. In fact, the crack growth resistance of this alloy appears to be higher than that of 316 SS in similar testing conditions. Moreover, when creep loading with hold (dwell) times of 60s or 600s were intercalated every fatigue cycle, the crack growth rates did not change significantly. The conclusion is that the tests performed revealed that the crack growth is insignificant during the creep portion of a loading cycle, as compared with the crack growth during the fatigue portion of the cycle. In general, Alloy 709 shows excellent resistance to creep deformations and creep crack growth up to 700°C.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Final Report For PDRD SR16009: Durable Water Splitting Using Thermochemical Cycles Of Nanostructured Metal Oxides

The Tritium Facility process for stripping tritium from the glovebox atmosphere currently relies on the use of hot magnesium beds (mag beds) to “crack” tritiated water, releasing hydrogen isotopes as a gas. This is a safe and effective process for recovering hydrogen isotopes from water for further processing. However, due to the thermodynamic properties of magnesium, mag beds are single use - once the magnesium metal is converted to magnesium oxide the bed must be replaced. Replacing mag beds is a labor-intensive and operationally complex task. In order to streamline operations and reduce costs, it is desirable to develop a reusable system that recovers hydrogen isotopes from water, while safely sequestering oxygen in a stable form. The following document reviews the results from the Plant Directed Research, Development, and Demonstration (PDRD) project “Durable Water Splitting using Thermochemical Cycles of Nanostructured Metal Oxides” (SR16009), which had the specific goal of developing a process for stripping tritium from the glovebox atmosphere that eliminates magnesium beds.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Extraction of Mercury Utilizing 3D Printed Media-Mercury Extraction Coalescer (MEC)

This project was undertaken to address the concern of mercury species present in chemical reprocessing facilities and environmental remediation sites. Typical elemental mercury removal is performed by steam stripping. As efficient as this process is, the vaporized elemental mercury is often condensed along with acidic condensate. The acidic conditions re-dissolve the elemental mercury, transferring it back into the aqueous stream, and undoing the energy-intensive steam stripping process. This project looked to design and produce a 3D printed component to act as a mercury vapor/liquid coalescer utilizing structural and chemical features to segregate elemental mercury from an aqueous solution or process offgas and improving elemental mercury retention and removal from the recirculated condensate stream. The aim of this project is to take inspiration from nature, for example the lotus leaf, and the advantage of advanced manufacturing techniques, in this case 3D printing, to produce a functional solution to a serious environmental issue, the accumulation of elemental mercury in aqueous environments.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Extraction of Mercury Utilizing 3D Printed Media – Mercury Extraction Coalescer (MEC) (Revision 1)

This project was undertaken to address the concern of mercury species present in chemical reprocessing facilities and environmental remediation sites. Typical elemental mercury removal is performed by steam stripping. As efficient as this process is, the vaporized elemental mercury is often condensed along with acidic condensate. The acidic conditions re­-dissolve the elemental mercury, transferring it back into the aqueous stream, and undoing the energy-intensive steam stripping process. This project looked to design and produce a 3D printed component to act as a mercury vapor/liquid coalescer utilizing structural and chemical features to segregate elemental mercury from an aqueous solution or process offgas and improving elemental mercury retention and removal from the recirculated condensate stream.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Systems Biology Towards a Continuous Platform for Biofuels Production

The goal of our project was to develop Bacillus megaterium as a host for continuous biofuel production coupled with in situ product extraction by supercritical (sc) CO 2 stripping. We aimed to develop a system that utilizes supercritical CO 2 (scCO 2 ) to address challenges associated with microbial contamination, product toxicity, and product recovery that currently limit the potential of advanced biofuel and bio-based chemical production. We proposed an interdisciplinary research and development effort involving bioprocess engineering, systems biology, and chemical separation engineering, centered around a recently isolated microorganism that is tolerant to scCO 2 . To this end we pursued a series of Aims and Sub-Aims with the ultimate goals of 1) determining the systems physiology of B. megaterium during growth under scCO 2 (Aim 1); 2) engineering heterologous butanol production pathways for anaerobic and aerobic expression in B. megaterium (Aims 1 & 2); 3) conducting de novo pathway engineering for biosynthesis of longer chain fuels (Aim 2); and 4) developing and modeling a two-phase stripping chemostat for continuous production of biofuels with in situ scCO 2 extraction (Aim 3).

09 BIOMASS FUELS↗

Understanding the Interactions of Seawater Ions with Amidoxime through X-Ray Crystallography

Insoluble polymer substrates functionalized with the amidoxime (R-C(NH 2 )=NOH) functional group have been demonstrated as a technically feasible platform for extracting uranium from seawater, a potential source of extremely abundant uranium for use as nuclear fuel. While it is possible to isolate macroscopic amounts of uranium from the ocean with a positive energy return on investment using these materials, both the economic and energetic costs are many times greater than those of terrestrial uranium mining. Currently, the major contribution to this cost is the production of the sorbent itself, so being able to recycle the sorbent even a small number of times will have a huge impact on lowering the cost of their use. However, amidoxime resins show capacity fading when stripped by strong acids, presently limiting their recyclability. Both alternative extractants and alternative elution chemistries are under development with promising results but are yet at too early a stage to make predictions about their ultimate success. Given the potentially huge impact of a successful recycling process on the viability of seawater extraction of uranium, there is a strong need to pursue additional routes to elution chemistry. During the course of this project, we studied the interactions of amidoxime-containing small molecules with the abundant metal ions in seawater, including Li, Na, K, Mg, Ca, Fe, Cu, and V, to understand the interactions of [UO 2 ] 2+ with amidoxime. By using small molecules with multiple adjacent functional groups, we crystallized the resulting metal complexes and used single crystal X-ray diffraction (SCXRD) as our primary tool for structural characterization. We also investigated the use of solutions of hydroxylammonium salts in weak acids as eluents for stripping and recycling amidoxime-based sorbents. The replacement of strong acids, which react with and destroy the amidoxime functional groups, with weak acids based on hydroxylammonium, a reagent that is actually used to make the amidoxime groups, is expected to avoid capacity loss on recycling and possibly even regenerate functionality that was lost due to exposure to the marine environment.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

Effect of Surface Roughness on Wind Turbine Performance

Wind farm operators observe production deficits as machines age. Quantifying deterioration on individual components is difficult, but one potential explanation is accumulation of blade surface roughness. Historically, wind turbine airfoils were designed for lift to be insensitive to roughness by simulating roughness with trip strips. However, roughness was still shown to negatively affect performance. Furthermore, experiments illustrated distributed roughness is not properly simulated by trip strips. To understand how real-world roughness affects performance, field measurements of turbine-blade roughness were made and simulated on a NACA 63 3 -418 airfoil in a wind tunnel. Insect roughness and paint chips were characterized and recreated as distributed roughness and a forward-facing step. Distributed roughness was tested in three heights and five density configurations. The model chord Reynolds number was varied between 0.8 to 4.8 x 10 6 . Measurements of lift, drag, pitching moment, and boundary-layer transition were completed. Results indicate minimal effect from paint-chip roughness. As distributed roughness height and density increase, lift-curve slope, maximum lift, and lift-to-drag ratio decrease. As Reynolds number increases, bypass transition occurs earlier. The critical roughness Reynolds number varies between 178 to 318, within the historical range. Little sensitivity to pressure gradient is observed. At a chord Reynolds number of 3.2 x 10 6 , the maximum lift-to-drag ratio decreases 40% for 140 m roughness, corresponding to a 2.3% loss in annual energy production. Simulated performance loss compares well to measured performance loss on an in-service wind turbine.

17 WIND ENERGY↗

Recovery of High Purity Rare Earth Elements (REE) from Coal Ash via a Novel Electrowinning Process (Final Report)

The goal of this project was to produce a high purity, separated (>90%) rare earth oxide (REO) product from coal-based sources. This product was achieved using the following three steps: 1. Battelle’s ADP: The ADP process involves pretreatment of ash (milling and caustic leaching), leaching of pretreated ash with nitric acid, roasting of loaded acid solution containing REE, and water leaching of residual from roasting step, resulting in a REE pregnant solution. 2. Solvent Extraction (SX) Upgrading: The SX involves the extraction of REE from a pregnant REE solution using an organic extractant (note after extraction, the aqueous phase was a residual solution and the organic phase contained REE), and stripping of REE from the organic phase product obtained from the extraction using an acid solution (the stripped solution was the final purified product containing REE, organic traces, and traces of other metals for further separation in the electrowinning process). 3. Rare Earth Salts’ (RES) Electrochemical Separation and Purification Process: The staged electrochemical process was separated REO products from the mixed REE solution. Testing by RES was also included in the investigation of options to minimize the solvent extraction steps. This report covers laboratory testing, production of a high purity coal-based REO, process design of the overall REE recovery and purification process, technoeconomic assessment (TEA), and a commercialization plan discussing the overall REE recovery and purification process.

01 COAL, LIGNITE, AND PEAT↗

Coupled Hydrothermal Extraction and Ligand-Associated Swellable Glass Media Recovery of Rare Earth Elements from Coal Fly Ash (Final Report)

Wayne State University (WSU) researchers, in collaboration with the University of California-Los Angeles (UCLA) and Los Alamos National Laboratory (LANL), have successfully developed a new sorbent media used in a process that concentrated the rare earth content in a coal fly ash sample from southeast MI by >350×, resulting in >13 wt% REO powder. The project developed a new DTPA-associated media that was used to concentrate total REEs. This project demonstrated a coupled hydrothermal extraction and solid-liquid recovery process that produced REO powder from raw fly ash while nearly eliminating the use of organic solvents. The project successfully: 1) identified a commercially viable ash supply with >$2.5 M in REO value being deposited monthly, 2) hydrothermally extracted >77% of REEs in coal fly ash (20% more than acid alone), 3) developed a new sorbent media that was used to concentrate REEs, 4) and engineered a process that resulted in a >13 wt% REO powder. The media also demonstrates a selectivity for mid and heavy REEs over Ce and La and the potential for use in separating individual rare earth elements. An invention disclosure for the sorbent media has been filed with WSU and a patent application will be submitted in the near future. The project examined the potential to couple hydrothermal leaching of coal fly ash with the engineering of a custom ligand-associated media to provide an organic solvent-free method of extracting and recovering REEs. Fly ash feedstock was collected from Detroit area coal-fired power plants, characterized for REE content, and subjected to a bench-top batch hydrothermal leaching/dissolution process inside custom-build pressure reactors at Los Alamos National Laboratory (LANL). This process applied a dissolution technique previously developed to process spent nuclear fuel and other nuclear materials. The modified ash was acidified and the resulting leachate was enriched with REEs along with Ca, Al, and Si. Ligands known to be effective in lanthanide/actinide separation were evaluated based on a series of criteria such as selectivity and association to organosilica through hydrophobicity. Batch experiments were conducted to establish the best conditions (e.g., pH, eluent, etc.) and best ligand systems for the effective extraction of REEs from the alkaline feed solution obtained from the hydrothermal leaching process. Once the organosilica-ligand extraction media was developed for REE concentration, an acidic solution was used to back extract and concentrate the REEs into a heavily REE-laden strip solution. The REEs in the strip solution were precipitated with oxalate to produce rare earth oxides.

01 COAL, LIGNITE, AND PEAT↗

Economic Extraction, Recovery and Upgrading of Rare Earth Elements from Coal-Based Resources

The overall objective of this project is to produce a rare earth elements product with greater than 8% rare earth elements from coal-based resources using an economically viable and environmentally benign processing methodology. The objective of the coal processing work will be to acquire appropriate coal feed and produce a viable clean coal product, a concentrated REE feed stream, and a pyrite stream (where available) that can be used to enhance leaching. The objective of the bio-oxidation portion of the project is to utilize bacteria to oxidize sulfide minerals and ferrous ions to ferric ions to accelerate leaching and remove the sulfides to prevent future acid mine drainage and related liabilities. The objective of the solution conditioning work is to remove iron and control leaching solution conditions to facilitate extraction of REEs without significant thorium extraction. The objective of the column leaching work is to engineer/model and simulate heap leaching to demonstrate low-cost extraction of REEs from coal-based resources. The objective of the solvent extraction work is to selectively extract and recover through controlled stripping of REEs that are solubilized through leaching. The objective of the precipitation portion of the project is to recover the REEs from the solvent extraction stripping solutions and dry them to achieve the final product of rare earth elements that is > 8 % REEs. The objective of the technical, economic, and environmental analysis is to determine the overall viability of the processing approach that is demonstrated in this project. This project encompasses a range of technologies that are currently in industrial practice that are applied and engineered to produce rare earth element product from coal feed sources. The potential sources include large coal feed resources in active coal mines in addition to coal waste. This technology involves the utilization of advanced coal processing technology that can be used to deliver clean coal for the market as well as rare-earth-element-bearing non-coal rock that is of the correct size for heap leaching applications in addition to providing concentrated sulfide minerals (for mid to high sulfur coals) for cleaner coal and for enhanced bio-oxidation to accelerate leaching of REEs from the non-coal rock. The removal of the sulfide minerals cleans the coal, accelerates subsequent REEs extraction, and it removes the future potential for most acid-rock drainage. (For low sulfur coals some pyrite may be purchased if needed.) The processing method also utilizes bio-oxidation to enhance ferric ion production to enhance leaching, while also consuming the sulfide mineral and its associated environmental liability. The project includes a technical, economic, and environmental analysis to facilitate an appropriate assessment of commercial viability for this processing technology.

01 COAL, LIGNITE, AND PEAT↗

Beam Losses for the PIP-III Linac to Recycler/Main Injector

The PIP-III linac produces 8 GeV H - beam for injection into the Recycler or Main Injector (MI). Beam losses throughout the system must remain low to ensure high intensity in the MI cycle and to manage radiation effects to acceptable levels, including enabling practical maintenance of the facility. Beam loss mechanisms in the system mageable maintStripping to H+ is needed, in a system that is vulnerable to magnetic stripping of H- in magnetic fields. The High power beam will heat stripping foils, perhaps unacceptably. The injection pulse is much longer than the MI circumference, so multiturn pulses with resulting heating and beam diffusion are required. We discuss beam loss related design considerations for the Linac-based scenario.

43 PARTICLE ACCELERATORS↗

Results of the Analyses of SMECT Mercury Sample Collected During Mercury Pump (MB1) Functional Check

A pump added to remove mercury from the sump of the Slurry Mix Evaporator Condensate Tank (SMECT) in DWPF was successfully tested in 2020, resulting in a sample of contaminated mercury obtained from the Mercury Purification Process (MPP) cell. The mercury in the sump of the SMECT was present as a result of steam stripping of sludge slurry in the Sludge Receipt and Adjustment Tank (SRAT) at DWPF. A schematic of the MPP system provided by DWPF personnel is shown in Appendix A. DWPF personnel supplied the following detailed description of the Hg sampling: “The sample provided is the result of DWPF extraction of mercury by means of the Mercury Pump-Water Cart. The Mercury Pump extracted the sample from the SMECT mercury sump. The pump uses pressurized water to transfer a small amount of mercury to a leachate bucket located at the Lab Mercury cell. The mercury and water were allowed to be self separated, and mercury was gravity decanted from the leachate bucket.” DWPF personnel indicate that the leachate bucket is equipped with both a top stopcock/drain and a lower/bottom stopcock/drain from which the mercury was decanted or drained out, while the separated water layer remained above the mercury during draining. The DWPF customer requested SRNL to analyze the sample for the following: gross alpha/nonvolatile beta analysis and perform a Toxicity Characteristic Leaching Procedure (TCLP) per the Environmental Protection Agency's Test Methods for Evaluating Solid Waste: Physical/Chemical Methods, SW-846. While the TCLP was preferred, a Total Metals analysis of the eight Resource Conservation and Recovery Act (RCRA) metals was deemed acceptable.2 The analytical data collected on this mercury sample will be used in planning for sample disposition as well to start a profile for future Hg disposition of Hg collected from steam stripping.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗