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Lagos, Leonel

Publications and source records attributed to Lagos, Leonel.

At least 55 records · Page 3

Panel Session 35: Panel: Graduating Students and New Scientists and Engineers - Wants and Needs - Are Companies Even Listening?

This panel focuses on new hires, graduating scientists and engineers having open lines of communication with employers. Considering the projected shortfalls in the workforce, effective communication of wants and needs of both the employer and employee must exist. Do these needs differ between industries and/or generations? Currently, it seems that both sides must work harder to achieve this level of communication. With this new approach, both sides can express their wants and needs for a more satisfied workforce and a better work environment. Presentations proposed include: 1 - Graduating Students and New Engineers - Wants and Needs - Are 'National Labs' Even Listening? (Michelle Bingham, Idaho National Laboratory (USA)); 2 - Graduating Students and New Engineers - Wants and Needs - Are Companies Even Listening? (Alexander Pappas, Washington River Protection Solutions (USA)); 3 - Graduating Students and New Engineers - Wants and Needs - Are the Government Agencies Even Listening? (Lisa Phillips, US DOE (USA)); 4 - Graduating Students and New Engineers - Wants and Needs - Are Companies Even Listening? (Silvina Di Pietro, Applied Research Center - FIU (USA), Ximena Lugo, Applied Research Center - FIU (USA))

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Panel Session 36: Panel: Young Professionals in Nuclear Science and Engineering an International Perspective

This panel focuses on the young professional views from around the world on radioactive waste management. An informal panel will enable these future leaders of our industry to share ideas and experiences and develop contacts within peer groups on a genuine international level. The informal and interactive panel format will stimulate valuable discussion among the participants and the audience. The panel will be led by young professionals who will actively encourage participation from all those attending. Mentoring will be discussed. This panel aims to encourage fresh thinking and provide an opportunity for an open and frank discussion of issues. Presentations proposed include: 1 - International Youth Nuclear Congress (Alexander Borovskis, AusYGN (Australia)); 2 - AECOM Early Career Professionals Technology Exchange (Natalie Young, Washington River Protection Solutions (USA)); 3 - Young Professionals in Nuclear Science and Engineering - An International Perspective (Shona Thompson, Canadian Nuclear Safety Commission (Canada))

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Panel Session 94: Nuclear and Industrial Robotics, Remote Systems and Emerging Technologies

This panel focused on the use and benefits of robotics in different nuclear environments. Examples of robotics deployed in nuclear environments that come from industry, academia, and the government were presented. It is through these varying perspectives that the panel participants will show the breath of nuclear robotics used across the world. Presentations proposed include: 1 - Robotics and Emerging Technologies at Assystem (Fanny Fouin, Assystem Energy and Infrastructure (United Kingdom)); 2 - An Undergraduate Perspective (Michael DiBono, Applied Research Center - FIU (USA)); 3 - US-ROK International Collaboration on Robotics and Remote Systems for D and D of NPPs (Young Soo Park, Argonne National Laboratory (USA)); 4 - EM's Historical Engagement with Robotics and Universities (Genia McKinley, US DOE (USA)); 5 - Robotic Systems for Environmental Remediation Applications (Leonel Lagos, Applied Research Center - FIU (USA)); 6 - Remote and Nuclear Challenges and Solutions at the Savannah River Site - SRS (Jean Plummer, Savannah River National Laboratory (USA)); 7 - Nuclear and Industrial Robotics, Remote Systems and Emerging Technologies Challenges, Opportunities and Prognostications (Kim 'KD' Auclair, KD Auclair and Associates LLC (USA))

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Human and Robotic Testing in Gloveboxes to Reduce Worker Fatigue - 19542

A DOE-sponsored study conducted by the Los Alamos National Laboratory reported that the incidence rate of repetitive stress injuries (RSI) during manipulation tasks in glovebox and hot cell workspaces increased from 22% after 1-2 hours of work per day to 50% after 3 hours of work per day due to fatigue, repetitive motion, and hyperextension. Robotics can be a viable solution to this issue as robotic manipulators and wearable robotic devices can provide effective assistance to alleviate the workload. In order to use the robotic devices, an initial study to detect the amount of fatigue experienced by the glovebox operators is essential. Hence, in the present research two objectives have been specified and investigated. These include the use of electromyography (EMG) sensors to precisely detect the fatigue in various hands, arm and shoulder muscles and; the use of dexterous robotic arm and hand combinations to effectively perform certain repetitive and monotonous tasks conducted inside an in-house glovebox constructed for the research. A UR5 robotic arm and an i-limb artificial hand have been used. Human tests included eight subjects and two customized glovebox tasks. Pilot scale test results indicate variation in the mean frequency which is an indication of the level of fatigue that occurred. (authors)

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Development of Robotic Crawlers for Inspection of Radioactive Waste Tanks and Transfer Lines - 19573

The leaks in the primary liner of Double Shell Tank (DST) 241-AY-102 have motivated a number of research efforts to develop inspection tools that can obtain information regarding the integrity of the Hanford DSTs. Recently, there have been additional concerns regarding the DST secondary liners as well various pipelines within the waste transfer system. Over the past few years, Florida International University (FIU) has developed a pneumatic pipe crawler that can navigate through 3- and 4-inch diameter pipes and provide visual feedback while traveling through pipelines in excess of 100 feet and multiple 90 degree elbows. Recent updates to the crawler include a new sensor module that can provide information regarding environmental conditions within the pipeline and a mapping of the interior surface of the line. The sensor module is a carousel type device that can rotate 360 degrees and is placed near the front of the 3- and 4- inch crawler. The module can house a number of sensors including temperature, pressure, radiation, Lidar, optical camera and an inertial measurement unit (IMU). The intent of the module is to improve the functionality of the crawler by providing environmental conditions within the pipe and internal surface topography maps that can assist in understanding potential wear, pitting or thinning of the pipe. In addition to the 3- and 4-inch crawler, FIU is developing a 6-inch crawler that utilizes the same principles as the smaller unit. The objective of this tool is to navigate through the 6-inch drain lines leading to the drain channels within the foundation underneath the secondary liner of the DSTs. This crawler will house a miniature rover that will be deployed at the end of the drain pipe, where it connects to the foundation. The miniature rover will operate upside down, via magnets, underneath the secondary liner within the drain slots and provide visual information regarding the condition of the secondary liner. Thinning of the secondary liner has been noted from the annulus of the some of the DSTs, but it is unclear if the thinning is isolated to locations near the annulus. (authors)

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Development of a Semi-autonomous Miniature Rover for Inspection of Double Shell Tank Floors - 19575

Leaks in the primary liner of double-shell tank (DST) 241-AY-102 at Hanford have prompted the need for the development of inspection tools that are able to access confined spaces around and underneath the tanks. Last year, Florida International University (FIU) has continued to improve inspection tools that were developed in the previous years, to ensure that the resultant tools are able to overcome the challenges posed by the DSTs. Experimental testing conducted last year at the full-scale sectional mock-up of the DST's refractory slots revealed some shortcomings of the miniature rover, particularly in traversing over weld seams of different heights. The weld seams are the results of welded steel plate-joints for the DST. It was advised by the site engineers that the weld seams height could range from 6.35 mm - 9.525 mm (1/4 to 3/8 inches), and with 12.7 mm (1/2 inches) width. As the rover traverses over a weld seam, the gap between the rover's magnets and tank surface increases, causing the adhesive force to drop. The rover loses its surface contact if this adhesive force drops below its weight, jeopardizing the inspection tasks. In this paper, we present the numerical studies to calculate the minimum magnetic force required for the miniature rover to traverse over weld seams with different heights and the corresponding modifications to the rover design. Initial bench scale tests were conducted using a steel bar with 5 welds of varying heights. The testing validated the results from the simulation studies and established the rover's capability in traversing weld seams. Another challenge for the miniature rover is the use of a joystick or keypad for manual control. Utilizing these controls will likely be difficult for the operators due to the tight channels underneath the tank. Having a semi-autonomous navigational capability would alleviate the complexity of the inspection tasks and allow the operator to focus on the channel inspection. The goal is to implement lane-keeping capability, akin to that of a driverless car, for the inspection tool, so that it will maintain its relative position with respect to the wall of the channels. Am image processing pipeline has been developed using both the Robot Operating System (ROS) and OpenCV to process the image stream coming from the onboard camera, for the purpose of lane identification. Additionally, a PID controller has been implemented to navigate the miniature rover along the central location of the detected lane, while allowing the operator to control the tool's forward and backward motion. (authors)

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Waste Information Management System with 2017-18 Waste Streams - 18302

The Waste Information Management System (WIMS) 2017-18 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 35 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and intermodal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)

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International Standards Development and Its Role in Transitioning D and D Technologies to Deployment - 18315

As the need to perform deactivation and decommissioning (D and D) of the most challenging nuclear facilities worldwide is growing, facilitating the integration of state-of-the-art, cutting edge technologies will be critically important to safely, effectively, and efficiently complete this mission. However, end users in the field face significant obstacles to integrating new technologies into cleanup initiatives. By leveraging the development of international standards and testing protocols, the risks associated with implementing new technologies can be mitigated and further support the need to update existing directives and guidance handbooks to account for the tremendous recent advancements in technology development. The American Society for Testing and Materials (ASTM) International's E10.03 Subcommittee on Radiological Protection for D and D of Nuclear Facilities and Components has begun the development of standard specifications and uniform testing protocols designed to support the nuclear industry's testing and evaluation requirements for D and D technologies. The vision of the E10.03 Subcommittee is to promulgate operationally relevant, uniform testing protocols that can be leveraged by the various technology innovation and development programs across the nuclear environmental management community, and support decision makers and end users with common references in the selection and employment of those standards and associated technologies. These standards could also serve as the basis for updating existing directives and guidance documents such as the various DOE handbooks to better account for the role of cutting edge technology, and facilitate / expedite lab to market efforts that result in improved returns on investment (ROIs) for technology development programs. (authors)

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Engineering Scale Testing of Robotic Inspection Tools for Double Shell Tanks at Hanford - 18349

Waste found in the annulus of the AY-102 double-shell tank (DST) at Hanford has prompted the need for the development of inspection tools that are able to access confined spaces around and underneath the tanks. During the last year, Florida International University (FIU) has been developing inspection tools that are capable of accessing the tank floors through the air supply line, the air refractory channels and the drain lines. This effort has led to the development of a pneumatic pipe crawler and a miniature rover. In this paper, updates to the inspection tool designs and the full scale testing of both systems are presented. The tools provide visual feedback for the operator, carrying with them onboard cameras and light sources. The images are streamed back live via a tether, which also provides power to the devices. To increase the sensing capabilities of both tools, temperature, humidity and radiation sensor modules are being integrated onto the developed systems, and can be interchanged depending on the inspection objectives. The miniature rover measures 7 cm in length and 3.8 cm in width, and travels upside down on the bottom of the tank to avoid debris accumulated in the channels. The video is also being processed real-time to provide control of the unit semi-autonomously. The pipe crawler measures approximately 76 cm in length and 6.4 cm in diameter, and travels using pneumatic actuators that emulate the peristaltic movement contractions typical of worm type robots. A full-scale sectional mock-up of the DST foundation, refractory system and annulus is currently being developed as a test-bed for the testing of the inspection tools. The intention of the test-bed is to demonstrate the viability of using both inspection tools in configurations similar to the actual tank. The test-bed includes a 2.43 m wide section of both tank liners, refractory channels and concrete foundation with drain slots. The test-bed is designed to be modular so that various plate thicknesses can be easily utilized and different refractory configurations can be incorporated. Currently, the refractory channels are of the tree type structure with turns that are approximately 30 degrees. Both inspection tools were demonstrated in the mock-up facility. The miniature rover ran successfully through the drain slots from the annulus to central plenum and had no issues making the 90-degree turns. The peristaltic crawler was able to navigate through the 7.62 cm air supply line from the annulus to the central plenum. (authors)

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Panel reports session

This section brings together the reports of the 31 panel sessions listed below: - Avoiding the Human Capital Cliff in the DOE (PS22); - Implementing Technically-Based Cleanup; US DOE Balancing Regulatory and Fiscal Complexity (PS24); - United Kingdom - Remediation of Sellafield Legacy Ponds and Silos (PS25); - Aligning Decision-Making to Deliver Timely Results in Large Clean-up Programs (PS38); - Transition to Government Owned-Contractor Operated Site at Canadian Nuclear Laboratories (PS39); - Emerging Middle East Nuclear States' Status and Plans (PS40); - NPP Panel on Waste Management (PS41); - Robotics - International Innovations in Robotic Decommissioning Technology (PS43); - Fukushima Panel (1/2): Japan Fukushima Daiichi Decommissioning Update (PS54); - Fukushima Panel (2/2): Update on the Revitalization of Fukushima and the Surrounding Area (PS55); - US DOE LLW On-Site Disposal: LLW Disposal Facility Federal Review Group Review Process (PS56); - Challenges in DOE HLW Tank Management: Facility Start-up and Waste Disposition (PS57); - Waste Management Planning for Utility Small Modular Reactors (PS58); - US Nuclear Power Plant Waste Management - LLW Disposal Issues (PS59); - DOE-EM Robotics and Emerging Technologies Road-map (4/8) (PS60); - Graduating Students and New Scientists and Engineers - Wants and Needs - Are Companies Even Listening? (PS63); - U.S. Nuclear Robotics: Yesterday, Today, Tomorrow (5/8) (PS74); - US DOE Mixed Waste: Proposals for Dealing with Problematic Waste Streams and Policy Changes (PS76); - Current and Emerging US NRC LLW Regulatory Topics (PS77); - Agency Perspectives (US and International) on the Use of Risk and Dose Assessment Tools (PS80); - Progress on Deep Repository Programs Around the World (PS81); - US DOE Procurement and Contracting Opportunities (PS82); - Collaboration across Borders to Deliver Cleanup and Decommissioning Challenges (PS93a); - DOE Mission Success through Application of Practices and Solutions (PS94); - Challenges in Cask Certification - International Perspectives (PS96); - Robotics: Leveraging Innovations in Science and Technology to Benefit Safety Performance (PS98); - DOE Panel: DOE EM Featured Office - Portsmouth/Paducah Project Office (PS109); - Robotics: Lessons Learned from Industrial Robotics Deployment that can be Applied to the Nuclear Field (PS110a); - Roundtable: DOE Radioactive Management - Energy Facility Contractors Group - Waste Management Working Group (EFCOG WMWG) (PS118); - Thursday Topical Session 'Management of Used Nuclear Fuel: Will the United States Reengage and Align with International Efforts' (PS124); - Remotely Operated Vehicles for Emergency, Disaster, and Operational Upset Response (PS125)

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Florida International University Research on Soil and Groundwater Contamination at DOE's Hanford and Savannah River Sites - 18547

Nuclear weapons production and other defense-related activities at U.S. Department of Energy (DOE) sites have resulted in radionuclide and heavy metal contamination in surface and subsurface environments nationwide. The DOE Office of Environmental Management (DOE EM) faces a number of environmental challenges that are technically complex and unique to EM with tremendous associated cleanup costs. The success of the DOE EM mission will require development and insertion of innovative approaches and novel technologies to address the significant challenges associated with the remaining cleanup of contaminated sites. A key focus of the applied research portfolio addresses data gaps related to the behavior and chemistry of radionuclides of concern as well as the co-mingling of these contaminants in groundwater at EM sites such as Hanford, Savannah River, Oak Ridge and others. Florida International University (FIU) is conducting research in conjunction with Pacific Northwest National Laboratory (PNNL) and savannah River National Laboratory (SRNL) scientists to support environmental remediation efforts at Hanford and SRS. This research is focused on remediation technologies for contaminated soil and groundwater as well as the assessment of the fate and transport of contaminants in the environment. The overall objective is to reduce contaminant mobility through the development and application of state-of-the-art scientific and environmental remediation technologies. The FIU strategy is to conduct basic science research that fills knowledge gaps and complements work conducted at DOE sites. Support to Hanford includes contributing to the understanding of {sup 99}Tc chemistry and the fate and transport mechanisms of co-mingled contaminants including {sup 99}Tc, U(VI), Cr, and iodine (I). FIU has also provided basic science research that supports a treatability study currently underway at Hanford, which uses ammonia gas injection to manipulate pH and immobilize U(VI) in the subsurface. In addition, support for long-term monitored natural attenuation is provided through geophysical research that monitors subsurface contaminant and microbial responses. Research to evaluate the environmental factors that control the fate and transport of contaminants and co-contaminants in soil and groundwater is being performed for SRS. This research has contributed to the development, design, and deployment of innovative strategies to enhance the natural attenuation processes and to validate novel in situ remediation technologies. The SRS EM test bed demonstrations directly benefit SRS cleanup initiatives. Current investigations focus on natural organic compounds, such as humate, as a potential amendment for the treatment of uranium in groundwater associated with the SRS F-Area Seepage Basins plume, investigates the synergy between humate and silica to optimize the pH adjustment strategy for uranium remediation and investigates the interaction of Tc and I with soil from the Four Mile Branch wetland. Collaborative relationships between FIU and the national laboratories have provided synergy and benefits over the years to FIU, the national laboratories, the DOE complex, and the DOE EM mission. By working closely with the national laboratories, FIU research is not only closely aligned with the cleanup mission priorities at the DOE sites, but complements and supports the work at national laboratories. This coordination and leveraging of research efforts results in time- and cost-savings, and accelerates progress in the DOE EM environmental restoration mission. (authors)

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Environmental and Radiological Readiness of Fixatives, Foams, and Intumescent Coatings for D and D Applications - 18553

During D and D operations of legacy nuclear facilities, the ability to effectively stabilize contamination in large cavities is a significant challenge. For items that must be removed, such as gloveboxes and entry hoods, a method of simply filling the volume to stabilize any residual contamination after contamination efforts have concluded would be of great benefit, and further the As Low As Reasonably Achievable (ALARA) culture of the DOE complex. The development, testing, and characterization of commercial fixatives and foams for applicability towards fixating contamination provides a potential structural reinforcement and fire resiliency in legacy nuclear facility equipment. Much of the equipment, such as gloveboxes, shielded cells, and radiological hoods left over from nuclear processing leave large cavities. Filling these voids after decontamination efforts provides a means of shielding workers from excess radiation exposure while immobilizing residual contamination. As such, we look to continue the development of fixatives/intumescent coatings from the previous year and test commercially available polymer-based foam products for use in filling these cavities, providing a secondary level of protection and shielding during the D and D process This research is funded as part of the In-Situ Decommissioning and Technology Development and sponsored by DOE- Office of Environmental Management Technology Development. (authors)

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International Training to Promote Successful Environmental Remediation Projects - 18636

The International Atomic Energy Agency (IAEA) supports the efforts of its Member States to manage their nuclear and radiological liabilities, including radioactive waste management, decommissioning of facilities, and remediation of contaminated sites. As part of a project addressing Constraints in Decommissioning and Environmental Remediation (the CIDER Project), the IAEA is developing initiatives to further support capacity development specifically to promote implementation of safe, appropriate, and cost-effective environmental remediation (ER) projects. The IAEA sponsors numerous initiatives to provide its Member States training on important topics related to ER. It has become clear in recent years, however, that the existing training should be augmented with more in-depth training to provide for the development of the critical expertise needed to address significant ER challenges. ER projects typically are very complex, requiring the integration of numerous scientific and engineering disciplines, along with effective project planning and management. There are many examples of ER projects where considerable work has been completed, qualified technical staff are available, and adequate funding has been obtained, yet actual progress towards a final solution has been limited. In such cases, it appears that a key barrier is the lack of capacity to develop strategies, make fully informed decisions, plan for and manage activities, and implement successful ER actions. In light of the above, the IAEA has placed a priority on capacity development across the broad spectrum of ER project implementation. Efforts are underway to develop a new training program to develop capacity at the institutional and individual levels to equip course graduates to effectively integrate all areas of expertise in the planning and execution of ER projects. The target audience includes decision-makers; project managers, planners, and implementers; and academics. The core capabilities to be developed via this program include knowledge and skills related to: (1) radiation issues and radionuclide behavior; (2) health and safety protection principles and requirements; (3) identification, evaluation, and selection of ER technologies and approaches; (4) ongoing, constructive dialogue with stakeholders; (5) project planning, management, and communication; (6) cost estimation and funding development; and (7) implementation of appropriate site monitoring activities. The IAEA is collaborating with multiple organizations to develop and implement this training program, to leverage existing training programs and materials, and to coordinate on the development of sustainable training solutions. This paper will present the status of this initiative and work accomplished thus far. (authors)

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Assessment of calcium addition on the removal of U(VI) in the alkaline conditions created by NH3 gas

Remediation of uranium (U) contamination in the deep vadose zone (VZ) sediments abundant in calcite mineral is a challenging task considering the formation of highly stable and mobile uranyl complexes with carbonate and calcium in pore water composition. There is a concern that uranium contamination in the VZ can serve as a continued source for groundwater pollution, creating a risk to human health and the environment through the groundwater pathway. This requires in-situ remediation of the radionuclide-contaminated VZ to convert soluble U species to low solubility precipitates that are stable in the natural environment. Injection of reactive gasses (e.g., NH3) is a promising technology to decrease U mobility in the unsaturated zone without the addition of liquid amendments. The NH3 injection creates alkaline conditions that can alter the sediment pore water composition due to a release of elements from minerals (via desorption and dissolution) that are present in the sediment. However, it is not known how VZ pore water constituents (Si, Al3+, HCO3 -, and Ca2 +) would affect U(VI) removal/precipitation in alkaline conditions. This study quantified the role of major pore water constituents typically present in the arid and semi-arid environments of the western regions of the U.S and identified solid uranium-bearing phases that could potentially precipitate from solutions approximating pore water compositions after pH manipulations via ammonia gas injections. Triplicate samples were prepared using six Si (5, 50 100, 150, 200, and 250 mM), six HCO3 - (0, 3, 25, 50, 75, and 100 mM), and two Ca2+ (5 and 10 mM) concentrations. The concentration of aluminum and uranium was kept constant at 5mM and 0.0084 mM, respectively, in all synthetic formulations tested. Results showed that the percentage of U(VI) removal was controlled by the Si/Al molar ratios and Ca2+ concentrations. Regardless of the bicarbonate concentration tested, the percentage of U(VI) removed increased as the Si/Al ratios were increased. However, higher Ca concentrations correlated with higher U(VI) removal, ranging between 96% and 99%, at low Si/Al ratios. The SEM images of dried precipitates displayed dense amorphous regions high in silica content, where EDS elemental analysis unveiled higher U atomic percentages. The formation of uranyl silicate and carbonate minerals was also predicted by the speciation modeling. XRD analysis revealed the presence of uranyl carbonate mineral phases (andersonite, grimselite); however, uranyl silicates predicted (Naboltwoodite) were not identified experimentally, possibly due to the amorphous nature of the silica solid phases observed in our experiments.

Katsenovich, Yelena↗

Waste Information Management System with 2016-17 Waste Streams - 17246

The Waste Information Management System (WIMS) 2016-17 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 35 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)

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Removal of U(VI) in the Alkaline Conditions Created by NH{sub 3} Gas - 17288

Injection of ammonia (NH{sub 3}) gas in the unsaturated zone is an innovative technology to mitigate uranium contamination in the presence of oxygenated, high-carbonate, alkaline soil, and pore water composition typical for the Hanford Site. A uranium-contaminated plume is a potential source for groundwater pollution due to migration of soluble uranium species towards the water table. This study evaluates the effect of various pore water constituents such as Ca, Al, Si and bicarbonate ions on changes in uranium concentrations in alkaline conditions, created by the injection of NH{sub 3} gas to be used to effectively mitigate uranium contamination in the vadose zone sediments. The main target in this research was the speciation modeling calculations conducted via the Geochemist Workbench (GWB) software. For this purpose, the GWB's database was updated with the most recently published U thermodynamic data on dissolution reactions and revised stability and solubility product constants. The simulations were carried out for varied pore water compositions with 5% of NH{sub 3}(g) to increase the initial pore water pH from 8.0 to 11.87. The model assumed the system is closed to the atmosphere; so, no exchange of CO{sub 2} with the atmosphere. The predicted U(VI) aqueous species and saturation indices [SI= log(IAP/Ksp)] were plotted as a function of pH values. The aqueous uranium carbonate species, UO{sub 2}(CO{sub 3}){sub 2}{sup 4-} and UO{sub 2}(CO{sub 3}){sub 2}{sup 2-}, were more abundant in the absence of Ca{sup 2+} and at a low bicarbonate concentration. In pore water compositions containing Ca{sup 2+} and HCO{sub 3}{sup -}, the major predicted aqueous species were Ca{sub 2}UO{sub 2}(CO{sub 3}){sub 3}{sup 0}, CaUO{sub 2}(CO{sub 3}){sub 2}, and UO{sub 2}(CO{sub 3}){sub 3}{sup -4}. Also, the speciation modeling predicted the formation of boltwoodite [Na,K(H{sub 3}O) UO{sub 2}(SiO{sub 4})], uranophane [Ca(UO{sub 2}){sub 2}(HSiO{sub 4}){sub 2} 5H{sub 2}O], and grimselite [NaK{sub 3}UO{sub 2}(CO{sub 3})3.H{sub 2}O] minerals. The computed saturation indices (SI) indicated saturation of boltwoodite minerals in the simulated Ca-free compositions at zero and low (0 and 2.9 mM) HCO{sub 3}{sup -} concentrations. In the presence of Ca ions, 5 mM and 10 mM, and similar HCO{sub 3}{sup -} concentrations, speciation modeling predicted the formation of uranophane. However, grimselite phase was prevailing when simulated solutions contained Ca{sup 2+} ions and higher bicarbonate concentrations of 50 mM. (authors)

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Waste Information Management System with 2015-16 Waste Streams - 16463

The Waste Information Management System (WIMS) 2015-16 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 35 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)

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Characterization of U(VI)-Bearing Precipitates Produced by Ammonia Gas Injection Technology for Unsaturated Sediments - 16600

The processing of irradiated fuel to extract plutonium for the nuclear arsenal has resulted in a legacy of uranium contamination in the vadose zone (VZ) of the Hanford 200 Area. This contamination is a potential source for groundwater contamination, posing a risk to receptors through water uptake from contaminated wells or discharges to surface water. The injection of reactive gases is an innovative technology being evaluated for reducing the mobility of radionuclide contaminants in the Hanford vadose zone. Ammonia (NH{sub 3}) gas in particular has been used to reduce uranium mobility in laboratory scale studies and is being evaluated for field scale application. The sediment of the Hanford vadose zone is composed of a complex of mineral phases including quartz, feldspar, mica, and calcium carbonates. The silica content in the 200 Area subsurface markedly outweighs the majority of elements, with aluminum following closely. The injection of ammonia gas into the vadose zone is associated with an increase in pH conditions as the gas partitions into the pore water. The resulting alkaline conditions significantly increase the solubility of some aluminum and silicate-containing minerals within the system. As pH decreases to natural conditions, the aluminosilicate minerals will precipitate, potentially coating and sequestering the uranium contaminants. Although previous laboratory scale tests have shown decreased uranium mobility, there are many questions regarding the application of the remediation method to 200 Area vadose zone conditions. In particular, additional testing is required to understand the impact of various environmental factors on the formation of uranium mineral phases with the application of the NH{sub 3} injection method. In order to answer some of the unknowns regarding this remediation technology for the 200 Area vadose zone, an effort was made to characterize the uranium-bearing precipitates being formed with the injection of ammonia gas. Rather than a sediment-water system, a synthetic pore water solution was prepared using the ion concentrations relevant to the 200 Area vadose zone. These solutions were limited to select constituents believed to play a major role in the remediation process. The use of this carefully composed solution allows for the thorough evaluation of the contribution the variable components make to the formation of the solid analyte. The characterization of solid samples was attempted using a host of complementary analytical techniques including scanning electron microscopy with energy dispersive spectroscopy (SEM-EDS) and X-ray diffraction (XRD). Though characterization of the samples is ongoing, the data produced thus far has allowed for the imaging and X-ray spectroscopy of the solid uranium phases produced as well as a tentative identification of cejkaite (Na{sub 4}(UO{sub 2})(CO{sub 3}){sub 3}) as the major uranium mineral phase. (authors)

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