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At least 1,063 records · Page 59

Capacitive chemical sensor

A microfabricated capacitive chemical sensor can be used as an autonomous chemical sensor or as an analyte-sensitive chemical preconcentrator in a larger microanalytical system. The capacitive chemical sensor detects changes in sensing film dielectric properties, such as the dielectric constant, conductivity, or dimensionality. These changes result from the interaction of a target analyte with the sensing film. This capability provides a low-power, self-heating chemical sensor suitable for remote and unattended sensing applications. The capacitive chemical sensor also enables a smart, analyte-sensitive chemical preconcentrator. After sorption of the sample by the sensing film, the film can be rapidly heated to release the sample for further analysis. Therefore, the capacitive chemical sensor can optimize the sample collection time prior to release to enable the rapid and accurate analysis of analytes by a microanalytical system.

47 OTHER INSTRUMENTATION↗

Nuclear radiation cleanup and uranium prospecting

Apparatus, systems, and methods for nuclear radiation cleanup and uranium prospecting include the steps of identifying an area; collecting samples; sample preparation; identification, assay, and analysis; and relating the samples to the area.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Update of the like-sign dimuon charge asymmetry measurement from the D0 experiment

The D0 Collaboration has published three measurements of the CP-violating like-sign dimuon charge asymmetry in p-pbar collisions at the Fermilab Tevatron collider. These measurements are significantly different from the standard model predictions. In this presentation, we discuss the status of the final measurement of this asymmetry and the expected improved sensitivities, using the full 10.4 inverse-fb data sample collected during Run II, and discuss its possible interpretations

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗

Nuclear radiation cleanup and uranium prospecting

Apparatus, systems, and methods for nuclear radiation cleanup and uranium prospecting include the steps of identifying an area; collecting samples; sample preparation; identification, assay, and analysis; and relating the samples to the area.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Make the World Safer from Nuclear Weapons

Senior Nuclear Scientist Ted Bowyer knows firsthand the challenges associated with protecting our nation. Ted and his colleagues help detect the proliferation of nuclear weapons. They developed award-winning technologies that give international treaty verification authorities “eyes and ears” around the globe. The instruments, located in 80 countries, help ensure compliance with the Comprehensive Nuclear Test-Ban Treaty, or CTBT. They are completely automated radionuclide monitoring systems that would detect airborne radioactive particles if a nuclear detonation occurred in the air, underground or at sea. Some samples collected through these technologies are sent to PNNL’s Shallow Underground Laboratory—the only certified U.S. radionuclide laboratory for the CTBT’s International Monitoring System Organization.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Detecting isotopologues of carbon dioxide in the atmosphere in concomitance of water or methane

A meteorological tower is provided in a flux site and a solar array is positioned on the tower to provide power. A laser on the tower receives power from the solar array and produces a laser beam. A multiplicity of individual laser absorption spectroscopy gas cells positioned on the meteorological tower collect samples of the atmosphere. An optical cable connects the laser to each of individual las cell and direct the laser beam into each cell. Each cell includes a multiplicity of mirrors positioned so that the laser beam makes a multiplicity of passes through the samples. An analyzer associated with the cells receives the laser beam after the laser beam has made the multiplicity of passes through the sample of the atmosphere and the analyzer detects concentrations of isotopes of carbon dioxide in the atmosphere in concomitance of other gas concentrations.

Bond, Tiziana C.↗

Super Hot EGS and the Newberry Deep Drilling Project

A productive geothermal well drilled into super-hot rock (SHR) with a temperature above 400°C will produce super-critical fluid. At a flow rate of 60 kg/s, a SHR well could produce 50 MWe compared to 5-7 MWe for the same flow at 200°C. Even though these deeper, super-hot wells will cost more, the high energy density means power produced by engineered geothermal systems (EGS) can meet the market ($46 MW-hr) by directly tapping the heat source. We propose a proof of concept where hot rock is close to the surface (~5 km), and the cost of drilling and EGS stimulation will be lowest. A suitable, ready-to-go SHR site is on Newberry Volcano, Oregon, one of the largest geothermal heat reservoirs in the USA, extensively studied for the last 40 years. Millions of dollars have already been invested in the site by private geothermal developers and the US Department of Energy (DOE), resulting in a ready-to-use facility with the necessary infrastructure, environmental permits, land commitments, and monitoring plans. The Newberry Deep Drilling Project (NDDP) will be located at an idle geothermal exploration well, NWG 46-16, drilled in 2008, 3500 m deep and 320°C at bottom, which will be deepened another 1000 to 1300 m to reach 500 °C. The original well was drilled with few lost circulation zones and the temperature profile indicates conductive heat flow. Compared to other SHR projects world-wide, this well would return more materials (cuttings, core and fluids) with more predictable drilling conditions, thus providing a suite of data near and across the brittle-ductile transition in silicarich rocks. After drilling, a hydraulic well stimulation will both change the pore pressure in fractures and cool the fracture walls resulting in permeability enhancement through both thermal fracturing, and hydro-shearing. The first step for the NDDP was an International Continental Drilling Program (ICDP) sponsored workshop held at the OSU-Cascades campus in Bend from Sept. 10-14, 2017. The workshop concluded by setting ambitious goals for NDDP: 1) test EGS above the critical point of water, 2) collect samples of rocks within the brittle-ductile transition, 3) investigate volcanic hazards, 4) study magmatic geomechanics, 5) calibrate geophysical imaging techniques, and 6) test technology for drilling, well completion, and geophysical monitoring in a very high temperature environment. The second step, completed January 15, 2018, was submitting a proposal to ICDP for 46-16 deepening. The next steps will be to continue building a team with project, technology, and investment partners to make NDDP a reality.

EGS, Geothermal, Newberry↗

Hafnium Isotope Ratio Method for Enhanced Safeguards at Research Reactors

Pacific Northwest National Laboratory (PNNL) is developing a Hafnium (Hf)-based, enhanced safeguards measure for the verification of energy production in a research reactor. Historically, verification of nuclear reactor use has been based on extracting and measuring physical samples from non-fuel components of the reactor. The Hafnium Isotope Ratio Method for Enhanced Safeguards (HIRMES) provides a means of verifying reactor operation based upon measuring the changes in isotopic ratios in purpose-built coupons. The first activity is installing a purpose-built, integrated sample collection coupon containing hafnium which undergoes isotopic changes when irradiated in the reactor. The second activity is analysis of the isotopic changes of the irradiated coupon after removal of the coupon using the isotope ratio method (IRM). The energy, or plutonium production, in a fission reactor can be estimated using IRM by measuring and correlating stable isotope ratios in non-fuel reactor components using standard reactor modelling methods. This paper presents HIRMES, a technology intended to provide an inexpensive, accurate, and robust measurement capability for validating operator declarations at low-power research reactors. Deploying HIRMES in research reactors would provide the IAEA with an in-core reactor “odometer” on total energy production with higher accuracy than other methods. HIRMES could be integrated in new fuel or reactor core designs as part of a protocol that is simple to implement and minimizes effort required of the operator or inspector. This paper also discusses early demonstrations at U.S. research reactors to-date, which demonstrate HIRMES as a practical tool for independent verification of low-power research reactor utilization. Specifically, the measurement uncertainty during an irradiation campaign of 39766 MWh was 22 MWh, representing two hours at a 10 MW reactor for a total irradiation campaign over the course of approximately six months.

research reactor safeguards, isotope ratio method↗

Toward Super Hot EGS: The Newberry Deep Drilling Project

Newberry Volcano in Central Oregon is an extensively studied volcano that contains one of the largest geothermal heat reservoirs in the western United States. The detailed characterization of this continental volcanic system reveals it is an excellent choice for drilling a well that will reach temperatures greater than 450°C at relatively shallow depths (< 5000 m). The main purpose of the Newberry Deep Drilling Project (NDDP) is to test the feasibility of super-hot EGS where super critical fluid can be produced with a higher energy compared to conventional EGS. NDDP will be located at an idle geothermal exploration well, NWG 46-16, drilled in 2008 on the western flank of the volcano. The project has several main goals: test EGS above the critical point of water; collect samples of rocks within the brittle-ductile transition zone; investigate volcanic hazards; study geomechanics in plastic rock and test technology for drilling, well completion, and geophysical monitoring. The well NWG 46-16, now 3500 m deep and 340-374°C at bottom, will be deepened another 1000 to 1300 m to reach 500°C into the supercritical region, and potentially approaching the brittle-ductile transition or even zones of partial melt. The original well was drilled with lost circulation zones only at very shallow depth and the temperature profile indicates conductive heat flow. Compared to other super-hot geothermal projects worldwide, this well would return more materials (cuttings, core and fluids) with more predictable drilling conditions, thus providing a suite of data near and across the brittle-ductile transition in silica-rich rocks. The well will be completed with casing and cement designed and tested to withstand the abuses of thermal cycling, hydraulic and thermal stimulation, and flow of supercritical fluids. Geothermal, volcanic, geophysical, and engineering information gained will be widely applicable to other magmatically active areas throughout the Pacific Rim and beyond.

EGS, supercritical, Newberry Volcano, brittle-duct↗

Pilot-Scale Testing of an Integrated Circuit for the Extraction of Rare Earth Minerals and Elements from Coal and Coal Byproducts Using Advanced Separation Technologies

The primary objective of this project was to develop and demonstrate an integrated pilot-scale circuitry for recovering high-value rare earth elements (REEs) from coal and coal byproducts. The target performance was to produce a mixed REE product with content of at least two percent by weight on a dry mass basis in a cost-effective and environmentally benign manner. During the first nine months of the project period (Phase 2 Budget Period 2), pilot plant construction was completed including all field site startup activities such as permitting, engineering design, procurement/bidding, unit fabrication, site construction, equipment installation, module assembly, safety training, and circuit shakedown. During the remaining 21 months of project period (Phase 2 Budget Period 3), detailed field-testing activities were performed including feedstock sample collection and preparation, exploratory testing, circuit modification, detailed parametric study, and performance optimization. A detailed techno-economic analysis was performed based on the pilot plant testing findings which provided various scenarios for REE production. The project successfully accomplished the proposed target performance by producing mixed rare earth oxide (REO) with greater than 90% purity by weight in a continuous pilot scale operation from two distinctly different coarse refuse materials (i.e., West Kentucky No. 13 and Fire Clay coal seams), and at least three secondary sources (i.e., heap leach process and naturally formed acid mine drainage system). Project partners included the University of Kentucky, Virginia Tech, West Virginia University, Alliance Coal, Blackhawk Mining, Mineral Refining Company, and Mineral Separation Technologies. The pilot scale test facility was constructed at a former mining complex owned by Alliance Natural Resource Partners (Alliance Coal). The site was rehabilitated to accommodate the equipment installation, construction and fabrication, electrical power requirement, water line management and containment. The process units constructed and installed included X-ray sorting unit, crushing and grinding unit, physical separation unit, acid leaching unit, solvent extraction unit, and wastewater management unit. A rare earth mineral concentration unit was constructed as a standalone unit for flexible operation. A detailed environmental assessment and control plan was carried out to identify and quantify any potential impacts of the pilot-scale processing circuitry on the human and eco-system health and well-being. Corresponding mitigation strategies and control measures were provided. A conceptual flowsheet was developed to effectively remove thorium and uranium from high purity rare earth oxide mix or any potential radionuclide enriched stream. The two distinct feedstock materials were secured from the Blackhawk Mining Complex in eastern Kentucky where the Fire Clay (Hazard No. 4) seam is processed. The West Kentucky No. 13 (Baker) coarse refuse material was collected from an active process stream at an Alliance coal preparation plant located in western Kentucky. Characterization analysis indicated that both of feed materials generated from the two sources contained >300 ppm of TREEs on a dry whole mass basis which met the requirements for a qualified feed stock. The two feedstocks were further upgraded using a dual x-ray sorter to prepare the feed material for hydrometallurgical circuit. Thermal treatment on feed material prior to leaching was found to: 1) improve the leaching recovery of REEs, 2) increase the leaching kinetics, and 3) allow the leaching reaction to occur at lower acidity. Roasting at 600°C was selected as the pre-treatment condition for both West Kentucky No. 13 and Fire Clay coarse refuse material. Over 40% of leaching recovery was achieved by roasting West Kentucky No. 13 material having a top particle size of 3 mm in the pilot scale operation using 1.2M sulfuric acid leaching at 75OC. Initial pilot scale testing involved continuous operation of the pilot plant for 94 hours. The leaching unit was operated at solid-to-liquid ratio of 1 to 10 (w/v) using 0.5M sulfuric acid solution at a temperature of 75°C. The continuous solvent extraction circuit utilized rougher and cleaner units with DEHPA and TBP as the extractants. An innovative stripping circuit was developed to accumulate the REE concentration in the stripping solution to a level above 600 ppm. A bleed stream from the recycled strip solution was treated using oxalic acid precipitation which produced a high grade rare earth oxalate. The oxalate product was roasted to remove the oxalate which produced a rare earth oxide product having a purity greater 90%. Due to high concentrations of contaminant ions in the pregnant leach solution (PLS), a modified flowsheet was developed that involved pre-concentration of the REEs using multiple stages of precipitation and redissolution. The advantage of this process was improved removal of contamination before the downstream purification process and a significant cost reduction relative to the circuit that utilized the solvent extraction process. The modified circuitry included processes involving leaching, multistage precipitation, redissolution, and oxalate precipitation followed by roasting of the oxalate product. The circuit produced a mixed REO that was 92.96% pure from the initial test. A detailed parametric test plan was carried out which involved varying key parameters including solids feed rate, acid flowrate, acid concentration, multistage precipitation pH, redissolution pH, oxalate precipitation dosage and pH. The response variables included REE recovery, contaminant recovery, REO product grade and overall chemical consumption. Test results indicated that the acid-to-solid ratio is the key parameter to leaching efficiency as performance deteriorated with an increase in solids concentration. The optimal pH determined for REE precipitation and redissolution was 6.5 and 2.5, respectively. Additional tests were conducted to further improve the flowsheet. Recirculating a portion of the PLS to the feed of the leach tanks improved the leaching performance by lowering the pH of the leaching system and reducing the contamination recovery by shortening the residence time. Moreover, the removal of Al prior to REE precipitation significantly reduced the oxalic acid consumption in the oxalate precipitation circuit. The modified circuit produced over 90% grade REO by weight from both West Kentucky No. 13 and Fire Clay coarse refuse material in pilot scale continuous test programs. A case analysis model was developed to project the REE and major contaminants concentration in each PLS stream based on the leaching condition, pH cut point, and oxalic acid dosage. A correlation was established using empirical and semi-empirical models. Using the models, chemical consumption required for each stage was predicted based on the projected performance of the hydrometallurgy circuit. After identifying the optimum conditions, validation tests were carried out for the treatment of both West Kentucky No. 13 and Fire Clay coarse refuse materials in the pilot plant. The actual circuit performance and chemical consumptions were very close to the model predictions. Other than the two coarse refuse sources, several secondary feedstocks were also tested in the pilot plant facility. A “heap leach” system was constructed using the coarse refuse material generated from cleaning the West Kentucky No. 13 seam coal. Using the two stage SX rougher and cleaner circuit, a concentrate with a grade >90% REO was produced while recovering >97% of the REEs from the heap leach PLS. Naturally generated acid mine drainage (AMD) from West Kentucky No.13 mine was processed using the multistage precipitation circuit in the pilot plant in a test conducted for a period of 32 hours. The final grade of the mix RE oxide produced from the AMD was 90.84% with an overall circuit recovery of 64%. The primary source of REE was the selective precipitation steps involving iron and aluminum rejection. The hydrophobic-hydrophilic separation (HHS) process was proven to effectively recover coal from fine waste materials. For REM recovery, the HHS process was able to produce concentrates at grades of approximately 1.8% REE on an ash basis; however, recovery values were typically low, <10%, under the optimal conditions determined in the laboratory-scale testing. Staged testing of the pilot-scale HHS process for coal recovery and semi-continuous laboratory testing for REM testing showed that a total concentration ratio of more than 15x was observed for the REM recovery process. A circuit simulation package was developed for REE extraction and purification using a spreadsheet-based platform (Microsoft Excel). The REESim circuit simulation package is configured to track the mass and volume flows of components passing through a series of unit operations specified and configured by the user. The mass rates can then be utilized by the user to determine important performance indicators such as product mass yields, concentrate purity levels, element-by-element recoveries, and so forth. The techno-economic analysis showed that the roasting and leaching operations were the most expensive capital items, each contributing approximately 30% to the total capital cost. One notable contributor to the high production costs was the low REE recovery observed in the pilot scale trials. The product basket price was shown to have a strong influence on the economic viability of the scenarios, with the scandium price being the most significant influencer. Operating cost was shown to be extremely sensitive to REE recovery, REE feed grade, and leaching acid consumption. An analysis of ten different scenarios for a 500 t/h commercial operation revealed that three were economically favorable, producing internal rates of return varying from 27.7% to 33.1% and payback periods of 4 to 5 years. The project successfully developed and demonstrated a process to recover REEs from coal and coal byproducts in a pilot-plant operation which consistently produced over 90% grade REO mix from varies types of feedstocks. Commercialization analysis showed that the technology readiness level successfully achieved TRL 6 at the end of the project and demonstrated the need and the potential for scaling the process to further advance the technologies toward the goal of providing a domestic supply of REEs at a commercial scale.

01 COAL, LIGNITE, AND PEAT↗

Identification and analysis of quasielastic neutrino interactions at MicroBooNE

The study of neutrino oscillations and the extraction of high-accuracy neutrino mixing angles, CP phases, and mass differences, are at the forefront of the worldwide current experimental physics research. Neutrino experiments aim towards a high-precision extraction of these parameters, which requires a good knowledge of the interaction with the detector and target materials. In the energy range most relevant for oscillation studies ($E_\nu \sim$ 0.3 to 3 GeV), the dominant neutrino nucleus interaction is quasi-elastic (QE) scattering. Charged-current quasielastic (CCQE) scattering is the process by which the neutrino produces a charged lepton and removes a single intact nucleon from the nucleus, without producing any additional particles. It is one of the simplest lepton--nucleus interactions in the energy regime relevant for neutrino oscillation experiments. This thesis describes the identification and analysis of CCQE events in a data sample collected in the MicroBooNE detector at Fermilab during 2016; It discusses the isolation of the signal and the background rejection, as well as the extraction of the exclusive flux--integrated cross--sections for neutrino CCQE scattering off argon, $\nu_{\mu} + ^{40}$Ar$\to \mu^{-} + p$, as a function of the kinematics of the outgoing particles emerging from the interaction. We extracted $ \frac{d\sigma}{dp_{\mu}}, \frac{d\sigma}{d\cos\theta_{\mu}}, \frac{d\sigma}{d\phi_{\mu}}$, and $ \frac{d\sigma}{dp_{p}}, \frac{d\sigma}{d\cos\theta_{p}}, \frac{d\sigma}{d\phi_{p}}$. Here $p_p$,$\theta_{p}$,$\phi_p$ ($p_\mu$,$\theta_{\mu}$,$\phi_\mu$) are the momentum and scattering angles of the outgoing proton (muon). The data are in good agreement with predictions of GENIE, the standard event generator used for neutrino oscillation studies. The data confirms and constrains calcu lations essential for the extraction of oscillation parameters.

Cohen, Erez O.↗

Application of On-Line Monitoring and Real-Time Characterization of Low Level Waste Samples from Hanford Tanks

Waste and treatment stream characterization is an essential part of safe, efficient, and cost-effective processing of Hanford materials. The demand for materials characterization, including chemical, radionuclide, and physical attributes during waste management, transfer, and staging operations in the Hanford tank farms, is expected to significantly increase as the U.S. Department of Energy Office of River Protection (ORP) progresses toward Hanford waste treatment and immobilization. The application of on-line monitoring can greatly improve operation timeframes and reduce costs by providing real-time data and supporting the reduction of necessary grab sample collection. Recently, our team applied Raman online monitoring and chemometric modeling to the supernate of Hanford tank 241-AP-105, and demonstrated the quantitative measurement of nine analytes within this waste. Application of this method has been expanded to additional Hanford tank wastes, AW-102 and AP-107. The performance of the process monitoring instruments and the accuracy of the chemometric models will be assessed. On-line monitoring results will be compared to anion results determined from the current standard, ion-chromatographic and inductively coupled plasma mass spectrometry methods. Comparisons of both determined values and uncertainties of results will be presented. Results will be shared with personnel working on flowsheet interfaces for the Direct-Feed Low Activity Waste mission at Hanford.

Lines, Amanda M.↗

Characterizing Reactor Operations from Realistic Simulated Environmental Samples: Combining High-Performance Computing and Data Analytics

Environmental sampling is a common technique employed by inspectors and facility operators in nuclear safeguards, proliferation detection, and process monitoring contexts. Interpreting measurements performed on samples or collections of samples and ensuring the information extracted is accurate and precise is difficult. To date, these analyses have relied on simulated data to enable systematic studies; however, these models are inherently limited by the fidelity of the models and the implicit spatial averaging of isotopic composition or other signatures of interest. To advance this capability, we have refined the spatial discretization and expanded the range of physics in the simulation codes we use to perform reactor simulations and depletion calculations. This allows us to generate data that are more representative of real environmental samples, especially for the length scale of the isotopic composition and associated variation. Accordingly, these new data allow a more realistic assessment of traditional and new data analytic analysis methods. Here we present motivation for developing reactor simulations using high-performance computing methods and resources, impacts of these new simulations on our assessment of data analysis and interpretation methods, and initial results of developing and systematically testing data analytic methods designed to overcome the challenges expected of real-world samples. We also quantify the performance of these analyses using defensible statistical methods.

Dayman, Ken J.↗

Mechanical Demolition of Buildings with Concrete Asbestos Board Siding: Methodology, Precautions, and Results at the Hanford Central Plateau - 12417

Since the start of its contract in 2008, the CH2M Hill Plateau Remediation Company (CH2M HILL) has demolished 25 buildings with concrete asbestos board (CAB) siding using mechanical means. While the asbestos contained in CAB siding is not friable in its manufactured form, concerns persist that mechanical methods of demolition have the potential to render the asbestos friable and airborne, therefore posing a health risk to demolition workers and the public. CH2M HILL's experience demonstrates that when carefully managed, mechanical demolition of CAB siding can be undertaken safely, successfully, and in compliance with regulatory requirements for the disposal of Class II Asbestos-Containing Material (ACM). While the number of buildings demolished at Hanford and the number of samples collected does not make a conclusive argument that CAB cannot be made friable with normal demolition techniques, it certainly provides a significant body of evidence for the success of the approach. Of course, there are many factors that affect how to demolish a structure and dispose of the waste. These factors will impact the success depending on each site. The most obvious factors which contribute to this success at Hanford are: 1. The availability of onsite waste disposal where the handling and cost of asbestos-containing waste is not much different than other potentially contaminated waste. Therefore, segregation of demolition debris from the potential asbestos contamination is not necessary from a debris handling or asbestos disposal aspect. 2. The space between structures is typically significant enough to allow for large exclusion zones. There are not many restrictions due to cohabitation issues or potential contamination of adjacent facilities. 3. The willingness of the regulators and client to understand the industrial safety issues associated with manual CAB removal. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Brine Availability Test in Salt, a Heated Borehole Experiment at the Waste Isolation Pilot Plant, New Mexico, USA - 20233

The Brine Availability Tests in Salt is a US Department of Energy Office of Nuclear Energy supported activity as part of the Spent Fuel and Waste Disposition Campaign where we are performing simultaneous heated and control experiments in adjacent horizontal boreholes in the WIPP Salt Disposal Investigation drifts as part of experimental Phase 1. Phase 1a of BATS, a low-cost, small spatial-scale experiment performed in order to design instrumentation and methods for further experimentation in the URL, has been completed (June 2018 - May 2019) and is described elsewhere. In coincidence with multiple physical parameters that will be measured over the duration of the experiment, we will be measuring the liquid and vapor phases of H{sub 2}O as well as its isotopic content (not measured in Phase 1a). Three different forms of water occur in natural salts: as fluid in macro scale (mm size) inclusions, as intergranular free H{sub 2}O and as H{sub 2}O incorporated in hydrous minerals. Each of these forms has potentially different stable isotope signatures and will be influenced differentially by heat induced transport and by interaction with introduced tracers. Continuous measurement of vapor phase H{sub 2}O isotopes during borehole heating will be impacted by several effects: 1) evaporation as liquid brine flows into the borehole and evaporates completely or partially into the dry N{sub 2} stream; 2) steam from dehydration of hydrous minerals, that may enter the borehole; and 3) hydrous minerals that may form in the borehole (preferentially incorporating heavier isotopes). The continuous time series collected over the course of the heating test will be combined with analyses of pre-test and post-test collected samples of test site salt to investigate the contributions of each of the three water types as H{sub 2}O is mobilized due to the effects of heating. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Machine Vision-based Robot Manipulators for Nuclear Applications - 20370

Decommissioning and dismantling of nuclear facilities are major challenges facing the nuclear industry. Robot manipulators with capabilities of restoring nuclear structures and significantly prolonging nuclear power generation in addition to their applications in decommissioning and dismantling (D and D) would immensely ease the above-mentioned challenge. Ability to remotely sense/monitor and analyze dangerous and hazardous environments such as nuclear reactors as well as performing reparatory tasks in such environments using robot manipulators require additional information from vision sensors. Structural sample collection and inspection as well as restoration require object and position information. Computer vision is used to obtain precise 3D position information. The current work uses the Sawyer robot with the integrated Cognex camera. The research presents an approach to facilitate and improve operations in a nuclear reactor using robotic vision control. The vision control system is modeled with Augmented Image Space-based visual servoing approach. Results showing accurate robot control. Object recognition is used to recognize the image and calculate it poses. To transform coordinates of the object's pose from the camera frame to the robotic frame transformation matrices are employed. Future work will employ a 3D camera (with depth information) using Denso robot. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Application of On-Line Monitoring and Real-Time Characterization of Low Level Waste Samples from Hanford Tanks - 20380

Waste and treatment stream characterization is an essential part of safe, efficient, and cost-effective processing of Hanford materials. The demand for materials characterization, including chemical, radionuclide, and physical attributes during waste management, transfer, and staging operations in the Hanford tank farms, is expected to significantly increase as the U.S. Department of Energy Office of River Protection (ORP) progresses toward Hanford waste treatment and immobilization. The application of on-line monitoring can greatly improve operation time frames and reduce costs by providing real-time data and supporting the reduction of necessary grab sample collection. Recently, our team applied Raman online monitoring and chemometric modeling to the supernate of Hanford tank 241-AP-105, and demonstrated the quantitative measurement of nine analytes within this waste. Application of this method has been expanded to additional Hanford tank wastes, AW-102 and AP-107. The performance of the process monitoring instruments and the accuracy of the chemometric models will be assessed. On-line monitoring results will be compared to anion results determined from the current standard, ion-chromatographic and inductively coupled plasma mass spectrometry methods. Comparisons of both determined values and uncertainties of results will be presented. Results will be shared with personnel working on flowsheet interfaces for the Direct-Feed Low Activity Waste mission at Hanford. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Sources of Conservatism in Making Corrective Action Decisions at the NNSS - 20477

During the course of closing nuclear testing release sites at the Nevada National Security Site (NNSS) under the Federal Facility Agreement and Consent Order (FFACO) using the Risk-Based Corrective Action (RBCA) evaluation process, conservative assumptions and estimates were used in many phases of the work. These assumptions and estimates were agreed to during Data Quality Objective (DQO) meetings and published in the FFACO documents. However, the potential cumulative effect of these multiple sources of conservatism was not evaluated. The RBCA process ensures that corrective action decisions minimize the risk of making Type I errors (not applying corrective action to areas that exceed action levels) at the expense of making Type II errors (applying corrective action to areas that do not exceed action levels). Rather than fully characterizing the spatial distribution of contaminants throughout each site, the RBCA process uses a bounding methodology that conservatively estimates spatial boundaries beyond which contamination is not present that exceed corrective action levels. This process accepts that these boundaries may encompass areas that do not exceed corrective action levels and, therefore, may be somewhat larger than for fully characterized sites. This is justified at sites where the reduction in investigation costs are more than any potential increase in corrective action costs. To minimize the risk of making Type I errors, conservatism was used throughout the process. This study documents the many sources of conservatism used in the RBCA process. Conservatism was used in the RBCA process in determining potential receptors, determining action levels, collecting samples, converting sample results into receptor dose, and accounting for uncertainty. This provides decision-makers with a high level of confidence that unacceptable risk to receptors will not result from exposure to residual contamination outside the corrective action boundaries. However, it does not provide an estimate of the actual extent of areas exceeding action levels. This study provides an evaluation of the effects of compounding conservatism on RBCA process decisions. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗