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At least 955 records · Page 53
All sourcesNASA NTRSDOE OSTI
DOE OSTI2022

Benchmarking and Exploring Parameter Space of the 2-Phase Bubble Tracking Model for Liquid Mercury Target Simulation

High intensity proton pulses strike the Spallation Neutron Source (SNS)’s mercury target to provide bright neutron beams. These strikes deposit extensive energy into the mercury and its steel vessel. Prediction of the resultant loading on the target is difficult when helium gas is intentionally injected into the mercury to reduce the loading and to mitigate the pitting damage on the vessel. A 2-phase material model that incorporates the Rayleigh-Plesset (R-P) model is expected to address this complex multi-physics dynamics problem by including the bubble dynamics in the liquid mercury. We present a study comparing the measured target strains in the SNS target station with the simulation results of the solid mechanics simulation framework. We investigate a wide range of various physical model parameters, including the number of bubble families, bubble size distribution, viscosity, surface tension, etc. to understand their impact on simulation accuracy. Our initial findings reveal that using 8-10 bubble families in the model renders a simulation strain envelope that covers the experimental ones. Further optimization studies are planned to predict the strain response more accurately.

Lin, Lianshan↗
DOE OSTI2013

Chooz A, First Pressurized Water Reactor to be Dismantled in France - 13445

Nine commercial nuclear power plants have been permanently shut down in France to date, of which the Chooz A plant underwent an extensive decommissioning and dismantling program. Chooz Nuclear Power Station is located in the municipality of Chooz, Ardennes region, in the northeast part of France. Chooz B1 and B2 are 1,500 megawatt electric (MWe) pressurized water reactors (PWRs) currently in operation. Chooz A, a 305 MWe PWR implanted in two caves within a hill, began operations in 1967 and closed in 1991, and will now become the first PWR in France to be fully dismantled. EDF CIDEN (Engineering Center for Dismantling and Environment) has awarded Westinghouse a contract for the dismantling of its Chooz A reactor vessel (RV). The project began in January 2010. Westinghouse is leading the project in a consortium with Nuvia France. The project scope includes overall project management, conditioning of the reactor vessel (RV) head, RV and RV internals segmentation, reactor nozzle cutting for lifting the RV out of the pit and seal it afterwards, dismantling of the RV thermal insulation, ALARA (As Low As Reasonably Achievable) forecast to ensure acceptable doses for the personnel, complementary vacuum cleaner to catch the chips during the segmentation work, needs and facilities, waste characterization and packaging, civil work modifications, licensing documentation. The RV and RV internals will be segmented based on the mechanical cutting technology that Westinghouse applied successfully for more than 13 years. The segmentation activities cover the cutting and packaging plan, tooling design and qualification, personnel training and site implementation. Since Chooz A is located inside two caves, the project will involve waste transportation from the reactor cave through long galleries to the waste buffer area. The project will end after the entire dismantling work is completed, and the waste storage is outside the caves and ready to be shipped either to the ANDRA (French National Radioactive Waste Management Agency) waste disposal facilities - (for low-level waste [LLW] and very low-level waste [VLLW], which are considered short lived) - or to the EDF Interim Storage Facility planned to be built on another site - (for low- and intermediate-level waste [LILW], which is considered long lived). The project has started with a detailed conceptual study that determines the step-by-step approach for dismantling the reactor and eventually supplying the packed containers ready for final disposal. All technical reports must be verified and approved by EDF and the French Nuclear Safety Authority before receiving the authorization to start the site work. The detailed conceptual study has been completed to date and equipment design and manufacturing is ongoing. This paper will present the conceptual design of the reactor internals segmentation and packaging process that will be implemented at Chooz A, including the planning, methodology, equipment, waste management, and packaging strategy. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

How Stakeholder Engagement is Evolving at the Caldas Uranium Mining Site in Minas Gerais, Brazil - 13223

The Caldas site is located in the Federal State of Minas Gerais in Brazil about 25 km from the city of Pocos de Caldas. While the city itself has 150,000 inhabitants there is a total population of around 0.5 million people living in an area that could potentially be influenced by the site. Uranium ore was mined and milled here between the years of 1982 and 1995, with ore extraction taking place from an open pit. Of the material removed, aside from that extracted for uranium, some was used on-site for road construction and building embankments while the remainder was disposed of onto two major rock piles. There are a number of potential historical and current environmental impacts to groundwater as a consequence of discharges into streams which then flow off site. The site is now undergoing a phase of decommissioning which includes the formulation and substantiation of a site remediation strategy. As part of a wider International Atomic Energy Agency (IAEA) Technical Cooperation Project aimed at providing practical guidance for implementing a decommissioning and remediation plan at the site, WSP E and E were invited to lead a mission in order to provide advice on the importance and merits of stakeholder engagement and how to ultimately build an engagement program. In November 2011, WSP E and E met with personnel from the site operators, the Brazilian regulatory bodies and representatives from the local stakeholder community and explained the principles of stakeholder engagement and how the process had internationally evolved principally from a decide-announce-defend approach to a more formal two way mechanism of engagement. Historically there had been insufficient liaison between the site operator, the nuclear regulator and the environmental regulator. All parties had recognized that greater interaction was necessary. There had also been very little engagement with local stakeholders about the various activities on the site and the potential implications of these activities on human health and the environment. The main concerns of the local stakeholders were in relation to potential environmental impacts on groundwater and surface water as well as their lack of knowledge about the site's activities and how it might evolve over time. There was a feeling that the site brought no real benefit to the local community as local labor was rarely utilized when work was being undertaken. WSP E and E were asked many questions about stakeholder engagement processes and had to address a number of concerns relating to being able to construct and control an engagement program. Advice was provided on how to construct a phased program in a manner that would allow the site operator to demonstrate increased transparency and allow as wide a range of stakeholders as possible the opportunity to become engaged. We provided an important message in that engagement often had to be culture and project specific and that what might work in one country could not necessarily purely be transposed to another. Since the WSP E and E mission there has been evidence of a number of positive steps in many of the areas of stakeholder engagement related to the Caldas site. The nuclear and environmental regulators work in a more open and transparent manner and continue to undertake joint inspections of the Caldas site. They have agreed to develop a written agreement that will enable them to jointly assess and discuss the issues on the site. Both regulatory bodies had previously accompanied the site operator on a visit to the Wismut uranium mining area in Germany and as well as providing useful learning had also allowed the regulators to discuss some common issues, thus bringing them closer together. A local stakeholder group under the auspices of the Water Commission had previously been set up but now they are starting to have more regular meetings with the site operator and nuclear regulator. They are now additionally considering the formation of a site specific advisory board (based on similar lines to those at US legacy sites) in order to gain some further technical focus within the stakeholder community. The site operator has started to present and explain the proposed environmental remediation plans to various towns and cities potentially influenced by the Caldas site. The successes to date can be attributed primarily to the willingness of the site operator to engage more openly with local community representatives in addition to the enthusiasm of the Water Commission itself. Providing stakeholder engagement advice to all the relevant parties in a manner which recognized their concerns, aspirations and country specific culture was extremely important for this positive progress to have been established. The process established and the subsequent successes could provide useful learning to those countries that face similar cultural engagement challenges. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2013

Use of InSpector{sup TM} 1 1000 Instrument with LaBr{sub 3} for Nuclear Criticality Safety (NCS) Applications at the Westinghouse Hematite Decommissioning Project (HDP) - 13132

The Westinghouse Hematite Decommissioning Project (HDP) is a former nuclear fuel cycle facility that is currently undergoing decommissioning. One aspect of the decommissioning scope is remediation of buried nuclear waste in unlined burial pits. The current Nuclear Criticality Safety program relies on application of criticality controls based on radiological setpoints from a 2 x 2 Sodium Iodide (NaI) detector. Because of the nature of the material buried (Low Enriched Uranium (LEU), depleted uranium, thorium, and radium) and the stringent threshold for application of criticality controls based on waste management (0.1 g {sup 235}U/L), a better method for {sup 235}U identification and quantification has been developed. This paper outlines the early stages of a quick, in-field nuclear material assay and {sup 235}U mass estimation process currently being deployed at HDP. Nuclear material initially classified such that NCS controls are necessary can be demonstrated not to require such controls and dispositioned as desired by project operations. Using Monte Carlo techniques and a high resolution Lanthanum Bromide (LaBr) detector with portable Multi-Channel Analyzer (MCA), a bounding {sup 235}U mass is assigned to basic geometries of nuclear material as it is excavated. The deployment of these methods and techniques has saved large amounts of time and money in the nuclear material remediation process. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

The 100-C-7 Remediation Project. An Overview of One of DOE's Largest Remediation Projects - 13260

The U.S. Department of Energy Richland Operations Office (RL), U.S. Environmental Protection Agency (EPA) and Washington Closure Hanford LLC (WCH) completed remediation of one of the largest waste sites in the U.S. Department of Energy complex. The waste site, 100-C-7, covers approximately 15 football fields and was excavated to a depth of 85 feet (groundwater). The project team removed a total of 2.3 million tons of clean and contaminated soil, concrete debris, and scrap metal. 100-C-7 lies in Hanford's 100 B/C Area, home to historic B and C Reactors. The waste site was excavated in two parts as 100-C-7 and 100-C-7:1. The pair of excavations appear like pit mines. Mining engineers were hired to design their tiered sides, with safety benches every 17 feet and service ramps which allowed equipment access to the bottom of the excavations. The overall cleanup project was conducted over a span of almost 10 years. A variety of site characterization, excavation, load-out and sampling methodologies were employed at various stages of remediation. Alternative technologies were screened and evaluated during the project. A new method for cost effectively treating soils was implemented - resulting in significant cost savings. Additional opportunities for minimizing waste streams and recycling were identified and effectively implemented by the project team. During the final phase of cleanup the project team applied lessons learned throughout the entire project to address the final, remaining source of chromium contamination. The C-7 cleanup now serves as a model for remediating extensive deep zone contamination sites at Hanford. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2021

Experience with Inner Reflector Plug exchange in SNS

The Inner Reflector Plug (IRP) is a central component of the Spallation Neutron Source target monolith, which houses the mercury target and four liter-sized neutron moderator units. It is exposed to high-level radiation fields during routine operation and builds up significant activity. The IRP needs to be replaced due to moderator neutron poison and decoupler burn-out, which is used for shaping neutron pulses. The first IRP exchange took place in March 2018. The old IRP was extracted from the target monolith, providing space for the new one. It was split into three segments, each of which was handled separately. The lowest section of the IRP is the largest segment in size and in activity and is temporarily stored on-site for cool down before conduction post irradiation examination. In support of planning the replacement activities, a wide range of activation and transport analyses were performed. This included calculating isotope inventories and the radiation fields for each segment as it is extracted in storage casks, and the radiation field from the empty IRP pit in the target monolith. While the replacement was taking place, measurements were performed and later on compared to the calculations. During these studies, it was discovered that a significant contributor to the radiation field from the lower IRP segment is from photo-neutrons. Photo-nuclear physics was added to the analyses and calculated results compared well with measured dose rates.

Popova, Irina I.↗
DOE OSTI2017

Long-Term Stewardship at a Former Uranium Mill Tailings Site in Riverton, Wyoming - 17090

The US Department of Energy Office of Legacy Management (LM) is responsible for maintaining protective public health and environmental conditions at former uranium mill tailings sites nationwide via long-term stewardship. One of these sites, a former uranium mill near Riverton, Wyoming, is within the boundary of the Wind River Indian Reservation and operated from 1958 to 1963. Tailings and contaminated material associated with mill operations were removed and transported to an offsite disposal cell in 1989. The remedial action was completed under Title I of the Uranium Mill Tailings Radiation Control Act of 1978. Milling operations, which included an unlined tailings impoundment and an unlined evaporation pond, contaminated the shallow groundwater, resulting in a down-gradient groundwater plume that discharges to the Little Wind River. A natural flushing compliance strategy was implemented in 1998. This strategy allows contaminants of concern to naturally flush from the groundwater, provided that contaminants flush below US Environmental Protection Agency maximum concentration limits within 100 years. As part of the compliance strategy, LM has implemented a groundwater monitoring program along with institutional controls that include the installation of an alternate water supply, continued sampling of private wells, and restrictions on well drilling and gravel pit construction. LM works closely with local stakeholders and community members to ensure that these institutional controls are in place and maintained. The Riverton site provides an interesting case study where contaminant remobilization due to river flooding prompted a reevaluation of the conceptual site model to verify if the current compliance strategy would remain protective of human health and the environment. Concentrations of groundwater contaminants, which include sulfate, molybdenum, and uranium, were transiently elevated following flooding of the Little Wind River in 2010 and 2016. These flood events provided the impetus to investigate other aspects of the hydrologic system, including the unsaturated zone, naturally reduced (sulfidic) zones, and evaporite deposits. New site conceptual models, field and laboratory studies, and numerical models are being developed to explain how biogeochemical sediment-water interactions contribute to plume persistence and flood-related increases in groundwater concentrations. Updated human health and ecological risk assessments are progressing to evaluate the risk to human health and the environment based on current site conditions. Groundwater concentrations may remain above US Environmental Protection Agency maximum concentration limits beyond the 100-year natural flushing regulatory time frame. LM in its capacity as a long-term steward continues to monitor the site to ensure protectiveness is maintained and to determine the feasibility of alternative compliance and remediation strategies. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Post-Closure Environmental Sampling and Inspection at the Amchitka Island, Alaska, Site - 17251

In the 1960's and early 1970's, three underground nuclear tests were conducted on Amchitka Island, Alaska. In 1965, the US Department of Defense-in conjunction with the US Atomic Energy Commission (AEC)-conducted the first of these nuclear tests, Long Shot, to provide data that would improve US capabilities for detecting underground nuclear explosions. In 1969, AEC conducted the second test, Milrow, to explore the feasibility of detonating a much larger device. In 1971, AEC conducted the third test, Cannikin, which was the largest underground test ever conducted by the US. The Long-Term Surveillance Plan (LTSP) for the Amchitka, Alaska, Site details how the US Department of Energy Office of Legacy Management (LM) intends to fulfill its mission to protect human health and the environment at and around the Amchitka Island site. The LTSP calls for monitoring to be performed every 5 years, at least during the initial phase of the project. The purpose of the monitoring is to develop a baseline of activity concentrations for selected radionuclides in biota, water, and soil, both on Amchitka Island and at the reference location on Adak Island, approximately 322 kilometers (200 miles) northeast of Amchitka. In addition to the environmental monitoring activities, seven mud pit caps that contain diesel-contaminated soils are inspected. The plan for biological and water sampling (both seawater and freshwater) during the May 2016 sampling event was developed through close coordination with the primary stakeholders, including the Alaska Department of Environmental Conservation, the Aleutian Pribilof Islands Association, and the US Fish and Wildlife Service. The environmental sampling in 2016 is a continuation of LM's evaluation of Amchitka Island's environment. Previous results from similar monitoring programs in 2004 and 2011 indicate that the environment is not being impacted by radionuclide migration and uptake from the underground nuclear testing conducted beneath Amchitka Island; consequently, subsistence and commercial-catch seafood is safe for human consumption. The collection of biota samples (rockfish, Irish lords, greenling, and rockweed) for cesium-134 ({sup 134}Cs), cesium-137 ({sup 137}Cs), plutonium-239 ({sup 239}Pu), plutonium-240 ({sup 240}Pu), and freshwater and seawater samples for {sup 134}Cs, {sup 137}Cs, and tritium ({sup 3}H) was the primary objective of the 2016 sampling effort. Rockfish, Irish lords, and greenling are resident, nonmigratory fish species that spend their entire life cycle in the marine environment, and rockweed is an inter-tidal species that may concentrate cesium. The seawater samples were collected primarily to determine if leakage from the Long Shot detonation could be detected and, secondarily, to compare with the background seawater samples collected from Adak Island. Cesium isotopes are also being analyzed to better understand the potential impact that the Fukushima-Daiichi release might have on the Amchitka and Adak environments. The target detection limits used for the 2016 sampling are lower than those used in previous studies. The lower detection limits make it possible for LM to delineate background activity levels for the radionuclides of interest. Data from the 2016 sampling event go beyond assessing food safety and focus on detecting leakage from the underground nuclear explosions. Additionally, the baseline activity concentrations obtained for the reference area (Adak Island) will enable identification of quantitative statistical trends in the results of future sampling programs. Sampling programs conducted in 2021 and beyond will have an objective to assess the statistical trends of radioactivity levels in the Amchitka Island environment. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Risk Assessment and Management of Uranium Mill Tailings Legacies - 17508

exploitation activities took place at 61 sites. The great majority of these mining sites are located in central-east Portugal, including the Urgeirica mine that was the most important uranium deposit exploited in the country. The mining activities at this site generated 1.6 million m{sup 3} of radioactive wastes disposed in an open air area originating the largest radioactive tailings pile of the country. The environmental remediation of the Urgeirica site was one of the main priorities of the national plan for the rehabilitation of former uranium mining sites. Site remediation, that included the mine industrial area with several support infrastructures and a processing plant, was executed between 2006 and 2008 (1. phase) and between 2008 and 2014 (2. phase). Nevertheless, the environmental rehabilitation of the Portuguese uranium legacies sites is not yet concluded. One of the last largest mining complexes, the Quinta do Bispo open pit, is scheduled to be rehabilitated only in 2020. This work presents a study to evaluate the environmental impacts from the uranium mill tailings legacies before and after the remediation works, focusing on two different approaches: a deterministic methodology for dose assessment and a probabilistic methodology with the Monte Carlo method to estimate the incremental lifetime risk. Probabilistic distributions of the input parameters were used in the risk calculation approach. The methodology for dose and risk assessments may be applied to other sites that are still under intervention and the results may be used to prioritize the remediation stages. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Latest experience from Jose Cabrera reactor vessel dismantling project - 15214

Westinghouse is performing a decommissioning project at the Jose Cabrera NPP in Spain. The project was awarded in June 2013 and the main scope is to cut and package the reactor vessel and the reactor vessel head. The project is performed in the necessary sequential steps needed to prepare, segment, separate, and package the individual component segments using under water mechanical techniques. The first activities to be performed on site included e.g. cutting of all pipe penetrations on the reactor, sealing of some of the pipe penetrations, lifting and transportation of the reactor and sealing of the reactor pit. The results of these activities were very good and gave a perfect foundation for the cutting and packaging of the reactor vessel. Cutting of the reactor vessel head and the reactor vessel is made with different types of Westinghouse designed cutting equipment. The flexible nature of the cutting equipment has proved to be very valuable for the execution of the cutting work. The project is planned to be finalized in April 2014. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2015

Hanford double-shell tank ultrasonic test examinations - 15287

Washington River Protection Solutions, LLC (WRPS) under contact from the US DOE is responsible for assessing the condition of the double-shell tanks (DSTs) of the Hanford Nuclear Site. WRPS contracted AVERA Federal Services, LLC to perform the ultrasonic testing inspections of the primary tank wall in 28 DSTs to access the condition of the tanks, judge the effects of past corrosion control practices, and satisfy a regulatory requirement to periodically (eight to ten year frequency) assess the integrity of the tanks per Brookhaven National Laboratory (BNL) guidelines for structural integrity programs for tank systems. The major requirements for the Ultrasonic Testing (UT) of each tank are to detect, characterize (identify, size and locate), and record measurements made of any wall thinning, pitting or cracks that might be present in the wall of the primary tank. The UT program examines representative areas of the primary tank and secondary liner by deploying equipment in the annulus of the tank through two 24-inch diameter risers approximately 180 deg. apart. From 1996 to 2006 the first-round of ultrasonic test inspections for all DSTs were completed utilizing a Pulse-Echo (P-Scan) system. The second round of ultrasonic test inspections have continued since 2007 and are complete for 26 of 28 tanks. The two remaining tanks will receive the second inspections during fiscal year 2015. Currently, the ultrasonic testing comparison results between the first and second rounds of inspection have identified no structural integrity concerns at action levels specified in the BNL guidelines. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Hanford double-shell tank testing program - 15341

The corrosion testing program and Hanford regularly tests waste chemistries to analyze threats and develop new corrosion chemistry guidelines. Over the past few years, the focus of testing has been on the threat of leaked wastes in Tank 241-AY-102 (AY-102). From the tests conducted to date, it appears that the potential waste compositions in the annulus of tank AY-102 do not show a propensity for localized corrosion or stress corrosion cracking. The threat of exterior corrosion from the liquid and moisture in the leak detection pit (LDP) is a potential concern that will continue to be evaluated in the coming year. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Analysis of erosion/corrosion data for high-level waste pipelines at Hanford - 15519

Washington River Protection Solutions (WRPS) has implemented a fitness-for-service program which will evaluate the degraded condition of the tank farm waste transfer system. The Tank Farms Waste Transfer System Fitness-for-Service Requirements and Recommendations, includes a requirement to inspect primary piping, encasements, and jumpers for corrosion/erosion. The 242-A Evaporator pump room was upgraded by adding instrumentation to the feed and return jumpers, prior to running the next campaign. As part of this upgrade, several jumpers were removed for disposal and a total of five jumpers were selected for ultrasonic thickness (UT) inspection. The jumpers selected were the following: 18-4, C-4 and 5, J-13A, 13-K, and 19-5. All of these jumpers will be removed permanently except for jumper 19-5 which will be reinstalled for further service. As part of this study, several jumpers from the AW-02E Feed Pit were also removed for disposal and two were selected for UT inspection. The jumpers selected were the 1-4 and B-2 which were packaged and sent to the 222-S Laboratory for UT assessments. This paper includes details of each jumper as well as the estimated remaining useful life (ERUL), if applicable, for its components based on the wall thinning measured in elbows and straight sections. The jumper's ultrasonic thickness measurements are plotted and trends are assessed based on the volume of fluid transferred or time of service. Variability in thickness is generally evaluated in two approaches, radially around the circumference of the pipe or component and longitudinally along the length. The paper also explains the analysis procedure for evaluating the different components. In particular, issues related to thinning from manufacturing different types of elbows (long radius, five diameter bend radius) are presented. Analysis techniques are developed for elbows that differentiate thinning from erosion/corrosion and manufacturing which is critical for this analysis. Results demonstrate that in most components, the thickness measurements are still greater than the manufactured nominal thickness. For the cases in which the thickness is below the nominal thickness, the ERUL well exceeds the life needed for servicing the Waste Treatment Plant. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Uranium mining and norm, a North American perspective - 15545

All soils and rocks contain naturally occurring radioactive materials (NORM). Many ores and raw materials contain relatively elevated levels of natural radionuclides and processing such materials can further increase the concentrations of natural radionuclides, sometimes referred to as technologically enhanced naturally occurring radioactive materials (TENORM). Examples of NORM minerals include uranium ores, monazite (a source of rare earth minerals), and phosphate rock used to produce phosphate fertilizer. Such activities have the potential to result in above background radiation exposure to workers and the public. Following a brief review of the sources and exposure from NORM in these varied industries, this paper will then present an overview of uranium mining and recovery in North America including discussion on the methods currently being used, production of NORM materials and wastes associated with these uranium recovery methods and the radiological composition of the NORM wastes produced by uranium recovery. The paper includes descriptions of the methods and associated NORM produced by both conventional (underground, open pit) and in situ recovery (ISR) mining methods and identifies the responsible government agencies in the US and Canada assigned the authority to regulate and control these NORM materials. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Boiling water reactor high flow filter system - 15683

Mechanical filtration is an essential element of industrial processes and operations. In the nuclear industry, mechanical filtration is particularly problematic because of the added challenge of minimizing personnel exposure and contamination associated with filter handling. Until recently, there has been no effective filtration system to maintain water clarity and minimize dose for diving operations in Torus/Suppression Pools, or for vacuuming operations to decontaminate Dryer Separation Pits during plant outages. To be effective, the filtration system must provide high flow to speed recovery from low visibility conditions. It must also have a high dirt loading capacity to minimize downtime during outage critical path. This paper looks at a new filtration system that has been introduced to the U.S. commercial nuclear power industry and used in numerous outages since 2012 and compares this Solids Collection Filter (SCF{sup TM}) system to previous filtration systems and practices and its impact on outage diving operations and decontamination efforts. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2015

Miniature motorized inspection tool for DOE Hanford site tank bottoms - 15700

Recently, small amounts of waste have been found in the annulus of tank AY-102, prompting the need for developing inspection tools that can identify the cause and location of the leak. Three separate access paths can be used to obtain information regarding the tank bottom condition. The inspection may be conducted via: 1) Refractory air slots through the annulus; 2) 4'' annulus air supply pipe to central air slots; 3) 6'' leak detection pit drain from the central sump. There are various environmental and physical constraints which the tool will have to adhere to. In order for the tool to be successful, it must be capable of the following: Travel through small cooling channels with dimensions as small as 1.5'' x 1.5''; Provide live video feedback; Produce enough torque to overcome the tether drag force; Inverted travel to avoid obstacles such as tank corrosion; Navigate up to 38 feet to the tank center, while maneuvering through four 90 deg. turns. A model of the inspection tool has been designed, assembled and reported. Areas of potential performance improvement were observed; these areas are the basis of the following design, as seen above. The changes include: The addition of an additional 4 wheels; Body modification to house the camera; A loft on the bottom from the tools edge to the magnets lowest edge; Shaving the hubs of the current wheels; Control method changed to a joystick. The tank configuration through which the tool will have to maneuver are the following: 72 outer ring slots (1.5'' x 1.5'' x 17'); 36 ring slots (2'' x 1.5'' x 12'); 18 inner slots (3'' x 1.5'' x 7'). The components used for this design iteration are not radiation hardened nor are they designed to withstand elevated temperatures. However, this prototype has been constructed with the final goal of being radiation hardened and able to withstand elevated temperatures in mind. The components that make up this design iteration are the following: Arduino Uno board with ATMega328 micro-controller; Joystick shield kit for the Arduino Uno; Eggsnow USB Borescope Endoscope 5.5 mm inspection camera; 136:1 Sub-micro Plastic Planetary Gearmotor; 14 x 4.5 mm wheels; 3D-printed body; 3D-printed free rolling shafts; Neodymium magnet - 1 h x 3/8 h x 1/16 h; 4.53 lb pull force. In the time to come, there are a few goals that are to be completed. The first group of tasks is associated with the testing and recording of data of the current prototype. This data will be analyzed and appropriate action will be taken based on the results of the testing. The testing will include simulating the challenges that the tool will face in the AY-102 tank. Working with the Hanford DOE site, a bag of Kaolin 2200 will be acquired to be used for the test bed to simulate tank conditions. Further modification will then be made to enable the tool to be able to maneuver through a 90 deg. turn. Completion of this task will be a major milestone, as this tool will be readily usable in the other tanks containing HLW; as other tanks will be easier to maneuver through.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Design and Construction of the Paddys Run Streambank Stabilization Project at the Fernald Preserve, Harrison, Ohio - 16165

The Fernald Preserve is a former uranium-processing plant that underwent extensive remediation pursuant to CERCLA and is now managed by the US DOE Office of Legacy Management. While remediation of buildings and soil contamination was completed in 2006, aquifer remediation is ongoing. Paddys Run is a second-order stream that runs to the south along the western side of the Fernald Preserve. The Paddys Run watershed encompasses nearly 41 km{sup 2} (16 mi{sup 2}), including most of the Fernald site. Field personnel conducting routine site inspections in March 2014 observed that Paddys Run was migrating east via bank erosion into the 'Pit 3 Swale', an area of known surface-water contamination. The soil there was certified pursuant to site regulatory agreements and meets all final remediation levels. However, weekly surface-water monitoring is conducted from two puddles within the swale area, when water that exceeds the final remediation levels is present. Paddys Run had migrated east approximately 4 m (13 ft) in 2 years and was approximately 29 m (95 ft) from the sample location. This rapid migration threatened existing conditions that allowed for continued monitoring of the swale area and also threatened Paddys Run water quality. Therefore, DOE and regulators determined that the east bank of Paddys Run required stabilization. This was accomplished with a design that included the following components: relocation of approximately 145 m (475 ft) of streambed 9 m (30 ft) west, installation of a rock toe along the east bank, installation of two cross-vane in-stream grade-control structures, stabilization of a portion of the east bank using soil encapsulated lifts, and regrading, seeding, and planting within remaining disturbed areas. In an effort to take advantage of low-flow conditions in Paddys Run, construction was initiated in September 2014. Weather delays and subsurface flow within the Paddys Run streambed resulted in an interim shutdown of the project area in December 2014. Construction activities resumed in April 2015, with completion in November 2015. To date, this stabilization project has been successful. The regraded bank and streambed have remained stable, and no compromise to installed cross-vanes, the rock toe, or the soil encapsulated lifts has been observed. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Determination of Erosion/Corrosion Rates in Hanford Tank Farms Radioactive Waste Transfer System Pipelines - 16395

The twenty-eight double-shell underground radioactive waste storage tanks at the U.S. Department of Energy's Hanford Site near Richland, WA are interconnected by the Waste Transfer System network of buried steel encased pipelines and pipe jumpers in below-grade pits. The pipeline material is stainless steel or carbon steel in 51 mm to 152 mm (2 in. to 6 in.) sizes. The pipelines carry slurries ranging up to 20 volume percent solids and supernatants with less than one volume percent solids at velocities necessary to prevent settling. The pipelines, installed between 1976 and 2011, were originally intended to last until the 2028 completion of the double-shell tank storage mission. The mission has been subsequently extended. In 2010 the Tank Operating Contractor began a systematic evaluation of the Waste Transfer System pipeline conditions applying guidelines from API 579-1/ASME FFS-1 (2007), Fitness-For- Service. Between 2010 and 2014 Fitness-for-Service examinations of the Waste Transfer System pipeline materials, sizes, and components were completed. In parallel, waste throughput histories were prepared allowing side-by-side pipeline wall thinning rate comparisons between carbon and stainless steel, slurries and supernatants and throughput volumes. The work showed that for transfer volumes up to 6.1 E+05 m{sup 3} (161 million gallons), the highest throughput of any pipeline segment examined, there has been no detectable wall thinning in either stainless or carbon steel pipeline material regardless of waste fluid characteristics or throughput. The paper describes the field and laboratory evaluation methods used for the Fitness-for-Service examinations, the results of the examinations, and the data reduction methodologies used to support Hanford Waste Transfer System pipeline wall thinning conclusions. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗