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DOE OSTI2015

Control room consolidation at Hanford tank farms for improved conduct of operation - 15345

Washington River Protection Solutions (WRPS) manages the underground waste storage tanks at the Hanford site in Washington State on behalf of the DOE Office of River Protection. There are 177 tanks distributed among 18 tank farms spread across an area of desert scrub covering about 20 square miles. A single evaporator facility supports the tanks to provide waste reduction activities. Farms and associated equipment, including exhausters, have been operated locally since installation. Upgrades over time introduced limited automation, but using inconsistent platforms, and providing isolated control locations around the farms. However, as the Tank Farms move from maintenance operations to production operations, with increased numbers of waste transfers and evaporator campaigns, and also prepare for integration with the adjacent Hanford Waste Treatment Plant, then operational improvements were planned and are being implemented. Infrastructure improvement projects included upgrades of control systems to a common platform, and installation of a fiber optic based local area network to the majority of farms, which together provided a distributed control system supporting tank farms. This new infrastructure provided the basis to propose consolidation of control and monitoring operations to a single location. More than a single location, the new Central Control Room was to increase effectiveness of operations by providing full status of all activities being performed across the Tank Farms and the Evaporator. The recent addition of productivity e-tools also would provide capability for management, supervisors and operators to make informed decisions regarding facility operations, through custom online applications designed to provide real time information derived from operational data. For example, tracking turnover activities between shifts, and maintaining compliance with limited conditions for operations. The Central Control Room would also have a single supervisor able to effectively manage the status of all assets and processes. The expected benefits of this arrangement include increased operator utility, increased situational awareness, improved response time for upset conditions, improvement in operator environment, and reductions in operating costs. The projected ROI for the Central Control Room when fully operational was projected to be about two years based on reduced costs from freeing up operations staff to perform other work plus the time and material savings realized by operations being performed with increased situational awareness. So the Central Control Room would become a hub for monitoring and controlling facility operations while responding to real time information affecting productivity and performance, from a centralized location customized to a fresh working environment. Over a 14-month period, WRPS developed the concept and engineering, procured over 500 items, modified and installed in renovated building, and completed transition and testing of this new Central Control Room, turning over the initial phase to Operations for 24/7 use in April 2014. (authors)

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DOE OSTI2015

Seismic design of a nuclear waste repository against an earthquake induced rock shear load - 15346

Concepts for isolation of spent nuclear fuel have been studied by organizations in countries that employ nuclear power. These concepts typically involve a deep geological repository in bedrock, with processed radioactive waste encased in deposition canisters emplaced in underground excavations and surrounded by clay-based buffer. This multi-barrier approach is intended to provide long-term isolation of the waste package from the biosphere. According to many statistics, there is a tendency toward increasing numbers of earthquakes in the Korean peninsula each year. If an earthquake induced rock shear load occurs at a repository site, the engineered barrier system (EBS) can be sheared, resulting in a pressure increased in the buffer material. This is expected to result in damage to the canisters. Therefore, because the damage, which can be fatal to a disposal canister, can be given in case an earthquake occurs, the method protecting the canisters safely is needed. In this paper, 'an earthquake-resistance type buffer' was proposed using a method for protection from earthquake damage. To aid in achieving this objective, we have developed a technique for estimating the behavior of the EBS affected by earthquake induced rock shear using an analysis method, such as finite element method. As a first step, experimental tests are performed for understanding the behavior of the buffer material. Comparing the results of the numerical simulations to the experimental results can be used to verity the reliability of the analysis model. Then we developed the real scale analysis model of a nuclear waste repository. The main parameter having an effect on the earthquake-resistant performance was analyzed and an earthquake-resistance proof type buffer was designed. To improve the earthquake-resistance performance, we designed the buffer by putting the low- density buffer between the canister and buffer. The simulation results show that the earthquake-resistant performance was improved by about 65%. (authors)

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DOE OSTI2015

Current status of R and D activities and future plan and role of JAEA's two generic URLs - 15356

The Japan Atomic Energy Agency (JAEA) has promoted R and D on geological disposal technology contribute to the implementation and safety regulation for high-level radioactive waste(HLW) disposal. JAEA launched two purpose-built generic URL projects to cover the diversity of geological environments in Japan, in accordance with 'Long-Term Program for Development and Utilization of Nuclear Energy' published in 1994 by the Japan Atomic Energy Commission. One is the Mizunami URL Project started in 1996. The Mizunami URL Project is a comprehensive geo-scientific research project investigating the deep underground environment within crystalline rock at Mizunami City in Gifu Prefecture, central Japan. The other one is the Horonobe URL Project started in 2001. The Horonobe URL Project consists of two major research areas, geo-scientific studies and R and D on geological disposal technology in the sedimentary rock environment at Horonobe Town in Hokkaido Prefecture, northern Japan. Both of the URL projects have been planned to proceed in three overlapping phases, 'Phase I: Surface-based investigation', 'Phase II: Construction' and 'Phase III: Operation', with a total duration of about 20 years. Currently, the construction of research galleries in both of the Mizunami and the Horonobe URLs has been completed to 500 m and 350 m depths, respectively. R and D activities in Phase III are being conducted at both URLs. According to the latest five-year plan, announced in September 2014, JAEA will promote R and D activities in Phase III including study of the effects of long-term evolution of the geological environment on geological characteristics such as groundwater flow and chemistry for reducing the uncertainty inherent in the evaluation of the long-term stability of the geological environment. This has been a very critical issue for HLW geological disposal in Japan after the Great East Japan Earthquake in 2011. Furthermore, JAEA will contribute to international cooperation especially with countries having a similar geological environment such as those in the Circum-Pacific area, development of human resources and communication amongst stakeholders through the generic URL projects. (authors)

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DOE OSTI2015

Long-term performance of engineered barriers for high-level waste repositories - 15358

The evolution of the engineered barrier system (EBS) of geological repositories for high-level radioactive waste (HLW) and spent fuel (SF) has been the subject of many national and international research programs during recent years. The emphasis of the research activities was on the elaboration of a detailed understanding of the complex coupled thermo-hydro-mechanical and -chemical (THM-C) processes, which are expected to evolve in the early post-closure period in the near field. From the perspective of radiological long-term safety, an in-depth understanding of these coupled processes is of great significance, because the evolution of the EBS during the early post-closure phase may have a non-negligible impact on the safety functions at later stages of the repository's lifetime. Process interactions during the re-saturation phase (heat pulse, gas generation, non-uniform water uptake from the host rock) could impair the homogeneity of the safety-relevant properties in the EBS (e.g. swelling pressure, hydraulic conductivity, diffusivity). The 7. Framework EURATOM PEBS project (long-term Performance of Engineered Barrier Systems) was initiated in 2010 and completed in March 2014. The project aimed at evaluating the sealing and barrier performance of clay-based EBS over time. The project approach included experiments, model development and consideration of the potential impact on long-term safety functions. The specific project aims were to: -deepen the understanding of the THM and THM-C evolution of the EBS system with time, - provide an enhanced quantitative basis for relating the evolutionary behavior to the safety functions, - clarify further the significance of residual uncertainties for long-term performance assessment. It can be concluded that uncertainties in process understanding occurring in the re-saturation period have been better constrained through PEBS studies, thus the uncertainties in the long-term performance of bentonite barriers have been reduced in some areas. Improvements are in the areas of evolution of materials properties and model development and testing at various scales. On-going in-situ experiments in underground research laboratories may play an important role in further confirming bentonite performance over periods of 10 - 20 years. (authors)

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DOE OSTI2015

Development of a backfill material for LILW and HLW disposal galleries in the current Belgian geological disposal concept - 15374

In Belgium, it is planned to dispose of long-lived and high-level waste in an underground facility. After disposal of the waste, the galleries will be backfilled to provide stability to the galleries and to limit the amount of voids in the repository. To achieve those goals, the backfill material has to have a good flowability, a negligible bleeding, and a limited shrinkage. A limited grain size is also required to allow the injection of the backfill material. Despite the fact that the backfill supports the gallery lining, its strength must be low enough to enable the retrieval of the waste packages. The backfill material has to be chemically compatible with the Boom Clay and the waste packages. This means that it should not unduly perturb the clay or disposal packages. The thermal conductivity of the backfill material in the galleries containing high-level and thus heat-generating waste must be high enough to allow sufficient dissipation of the decay heat into the surrounding clay. Based on these objectives, material requirements were specified and the development of a backfill mixture was carried out. Initially, the mix composition was optimized in the laboratory. Thereafter, the backfill process of a gallery section was simulated. The investigations illustrate that this mixture can be transported via pipelines through the shaft and drifts and would fill completely the backfill sections in the galleries. Measurements of the porosity, the pore solution composition, the thermal material properties, and the strength illustrate the compliancies with the requirements and the feasibility of backfilling the disposal galleries. (authors)

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DOE OSTI2015

Department of energy tank closure - an examination of alternative approaches - 15390

Closure of single- and double-shell underground storage tanks at sites across the DOE complex poses a unique technical and regulatory challenge. Some sludge waste residues invariably remain in a tank after waste retrieval - especially in tanks with obstructions or associated piping. In addition, reducing the volume of these waste residues becomes increasingly difficult depending on the constituents and the age of the heel. This paper discusses tank cleaning and closure alternatives to allow a more efficient retrieval and characterization of the tank wastes. The paper also examines the possible use of a tank closure strategy that is informed by risk rather than subjective criteria. Gaps in the technical foundation supporting tank retrieval and closure have traditionally resulted in a number of overly conservative assumptions in performance assessments. An alternate tank closure approach would be to develop a scientific basis for tank closure which may allow greater waste volumes to be left in the tanks post-retrieval, while increasing protectiveness to human health and the environment. The approach is to characterize complex residual tank waste solids, measure contaminant release rates as a function of chemical environment, and build mechanistic release models. (authors)

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DOE OSTI2015

In-service inspection of radioactive waste tanks at the Savannah River Site - 15410

Liquid radioactive wastes from the Savannah River Site (SRS) separation process are stored in large underground carbon steel tanks. The high level wastes are processed in several of the tanks and then transferred by piping to other site facilities for further processing before they are stabilized in a vitrified or grout waste form. Based on waste removal and processing schedules, many of the tanks, will be required to be in service for times exceeding the initial intended life. Until the waste is removed from storage, transferred, and processed, the materials and structures of the tanks must maintain a confinement function by providing a barrier to the environment and by maintaining acceptable structural stability during design basis events, which include loadings from both normal service and abnormal (e.g., earthquake) conditions. A structural integrity program is in place to maintain the structural and leak integrity functions of these waste tanks throughout their intended service life. In-service inspection (ISI) is an essential element of a comprehensive structural integrity program for the waste tanks at the Savannah River Site (SRS). The ISI program was developed to determine the degree of degradation the waste tanks have experienced due to service conditions. As a result of the inspections, an assessment can be made of the effectiveness of corrosion controls for the waste chemistry, which precludes accelerated localized and general corrosion of the waste tanks. Ultrasonic inspections (UT) are performed to detect and quantify the degree of general wall thinning, pitting and cracking as a measure of tank degradation. The results from these inspections through 2013, for the 27 Type III/IIIA tanks, indicate no reportable in-service corrosion degradation in the primary tank (i.e., general, pitting, or cracking). The average wall thickness for all tanks remains above the manufactured nominal thickness minus 0.25 millimeter and the largest pit identified is approximately 1.70 millimeter deep (i.e., less than 10% through-wall). Improvements to the inspection program were recently instituted to provide additional confidence in the degradation rates. Thickness measurements from a single vertical strip along the accessible height of the primary tank have been used as a baseline to compare historical measurements. Changes in wall thickness and pit depths along this vertical strip are utilized to estimate the rate of corrosion degradation. An independent review of the ISI program methodology, results, and path forward was held in August 2009. The review recommended statistical sampling of the tanks to improve the confidence of the single strip inspection program. The statistical sampling plan required that SRS increase the amount of area scanned per tank. Therefore, in addition to the baseline vertical strip that is obtained for historical comparisons, four additional randomly selected vertical strips are inspected. To date, a total of 104 independent vertical strips along the height of the primary tank have been completed. A statistical analysis of the data indicates that at this coverage level there is a 99.5% confidence level that one of the worst 5% of all the vertical strips was inspected. That is, there is a relatively high likelihood that the SRS inspection program has covered one of the most corroded areas of any of the Type III/IIIA waste tanks. These data further support the conclusion that there are no significant indications of wall thinning or pitting. Random sampling will continue to increase the confidence that one of the worst 5% has been inspected. In order to obtain the additional vertical strips, and minimize budget and schedule impacts, data collection speed for the UT system was optimized. Prior to 2009, the system collected data at a rate of 32 square centimeters per minute. The scan rate was increased to 129 - 160 square centimeters per minute by increasing the scanner step and pixel sizes in the data acquisition set-up. Laboratory testing was utilized to optimize the scan index/pixel size such that the requirements for wall thinning and pit detection were still maintained. SRS continues to evaluate improvements to ultrasonic equipment. (authors)

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DOE OSTI2015

Diversity and the citizens' advisory board: aligning disparate views for better results - 15469

The Northern New Mexico Citizens' Advisory Board (NNMCAB) is a group of -citizen experts,- i.e., experts on being citizens who take the time and focus their attention to grow more informed about nuclear science, nuclear waste remediation, and environmental monitoring issues. The Board digests complex information associated with these topics in light of the Los Alamos National Laboratory's (LANL) and Department of Energy's (DOE) activities in Northern New Mexico and discusses and conveys this information clearly to a diverse regional stakeholder population that includes a 400+ year old Hispanic culture, a 1,000+ year old Native American pueblo culture, a highly educated scientific and technical community of federal workers and their families, rural agricultural communities, creative/artistic communities, and political and peace activists. Our Board has either representation from each of these diverse New Mexican sectors or enjoys public comment from these sectors. Projects that involve such stakeholder-expert exchanges include remediation of an underground chromium plume, continued investigation and remediation associated with a radiation leak at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, the transport of Transuranic Waste off the Los Alamos 'Hill,- the ultimate disposition of -33 Shafts,- currently in place at Los Alamos National Laboratory, and the distilled voice of the citizen for continued and sufficient federal funding each year for responsible clean-up and monitoring of nuclear activities. Through the NNMCAB's communication venue of regular public meetings, mis-characterization is prevented, public input is incorporated into the official record, and recommendations to the DOE are promulgated. Scientific and technical experts join the bi-monthly NNMCAB meetings and monthly committee meetings to present and discuss current topics. The availability of these experts and their deeper reference materials is key to the interchange, as is the respectful and patient dialogue that exists between board members and the subject matter experts, both in the public forums and between meetings. Meetings are professionally organized and orchestrated to maximize the value of the experts' and board members' participation time. The professional format of the meetings ensures maximum learning and relationship-building which fosters effective channels for public dialogue. (authors)

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DOE OSTI2015

Gas retention and release from Hanford Site sludge waste tanks - 15491

Radioactive wastes from nuclear fuel processing are stored in large underground storage tanks at the Hanford Site. Solid wastes can be divided into salt-cake (mostly precipitated soluble sodium nitrate and nitrite salts with some interstitial liquid consisting of concentrated salt solutions) and sludge (mostly low solubility aluminum and iron compounds with relatively dilute interstitial liquid). Waste generates hydrogen through the radiolysis of water and organic compounds, radio-thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Nonflammable gases, such as nitrous oxide and nitrogen, are also produced. Additional flammable gases (e.g., ammonia and methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Six double-shell tanks (DSTs) containing salt-cake wastes began showing signs of gas accumulation and buoyant instability in the form of periodic waste level drops in the 1980's. Studies in the 1990's indicated that gas would accumulate in the settled solids layer until its bulk density was lower than the supernatant liquid. The resultant gas release caused by this instability was termed a Buoyant Displacement Gas Release Event (BDGRE). Criteria were developed to prevent forming additional waste tanks that exhibited BDGREs. Significant gas accumulation and BDGREs were never observed in tanks containing predominantly sludge wastes. Literature reviews, data from Hanford Site waste tanks, and experiments with waste simulants have led to new conclusions on gas retention and release in sludge waste. The data show similar overall behavior where initially the settled solids volume increases as gas bubbles form. Gas fraction in the settled solids increases to a peak concentration after which additional generated gas escapes through connected cracks and there is a balance between gas generation and gas release with little change in gas fraction. Experiments showed that this behavior does not change as sludge waste depth increases. Sufficient data now exist to differentiate between gas retention and release behavior in Hanford Site sludge waste tanks and salt-cake waste tanks. The salt-cake criteria do not need to be applied to sludge waste tanks that exhibit certain gas retention and release behavior. Criteria for waste characteristics and process behavior have been defined that identify specific wastes and tanks that, based on previous operating experience, will have low gas retention and will not exhibit large, spontaneous releases. The first criterion defines what waste is considered sludge and what waste is considered salt-cake. If the mass ratio of soluble to insoluble constituents is below 2.5, then the waste is sludge. The second criterion is a density difference criterion that prevents tanks being operated in a region where sludge buoyancy might occur. For large gas releases to occur, the settled solids must accumulate sufficient gas to become less dense than the overlying supernatant (i.e., the settled solids would become buoyant). Based on previous operating experience, the ratio of liquid density to degassed settled solids bulk density (ρl/ρB) should be maintained at ≤ 0.84. This ensures that retained gas content in the sludge would need to exceed 16% by volume for the settled solids to become buoyant in the overlying supernatant. Tank waste that satisfies the mass ratio criterion, the liquid to bulk solids density criterion, and has process data supporting typical Hanford waste sludge behavior does not pose a significant risk for a large spontaneous gas release event. (authors)

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DOE OSTI2015

Environmental cleanup of the East Tennessee Technology Park - Year three - A status report - 15522

On August 1, 2011, URS - CH2M Oak Ridge LLC (UCOR) began its five-year, $1.4 billion cleanup of the East Tennessee Technology Park (ETTP), the former Oak Ridge Gaseous Diffusion Plant, located on the U.S. Department of Energy's (DOE) Oak Ridge Reservation (Reservation) in Tennessee. Under the contract, the base period scope of work to be completed by 2016 includes demolition of both the K-25 and K-31 gaseous diffusion buildings and all demolition waste dispositioned, initiation of demolition on the remaining K-27 gaseous diffusion building, safe storage of transuranic (TRU) waste for eventual transfer to the Transuranic Waste Processing Center, previously designated -No-Path-To-Disposition Waste- dispositioned to the extent possible, and completion of design and engineering of a mercury treatment system to be installed at the Y-12 National Security Complex (Y-12). UCOR will have also managed DOE Oak Ridge Office of Environmental Management (OREM)-owned facilities at ETTP, Oak Ridge National Laboratory (ORNL), and Y-12 in a safe and cost-effective manner. Since assuming responsibilities as the ETTP and Oak Ridge Reservation cleanup contractor, UCOR has completed its life-cycle Performance Measurement Baseline; received its Earned Value Management System (EVMS) certification; completed the deactivation and demolition (D and D) of the 44-acre K-25 gaseous diffusion building; removed and disposed of a contaminated underground storage tank (Tank W-1A) at ORNL; dispositioned mercury-contaminated storage tanks at Y-12; completed closure of the Toxic Substances Control Act Incinerator; disposed of more than 158,000 cubic yards of cleanup waste while managing the on-site Environmental Management Waste Management Facility (EMWMF); and conducted operations, surveillance, and maintenance activities at 180 DOE EM facilities at ETTP, ORNL, and Y-12 in a safe and cost-effective manner. In 2014, UCOR completed the removal and disposal of all of the K-25 demolition debris; completed the removal of asbestos-laden transite siding on the K-31 gaseous diffusion building and began demolition of that 17-acre building; advanced the characterization and deactivation of the K-27 gaseous diffusion building, readying the building for the start of demolition in 2015; advanced the design and engineering of a Mercury Treatment Facility to be located at Y-12; continued the cost-effective and safe disposition of all cleanup wastes; and readied ETTP for Voluntary Protection Program Star Status Assessment in 2015. Project performance as of December 31, 2014, continued to be excellent: - Cost Performance Index - 1.12 - Schedule Performance Index - 1.02 At the same time, since safety is the foundation of all cleanup work, UCOR's safety record goes hand-in-hand with its excellent project performance. Through calendar year 2014, UCOR's recordable injury rate was 1.04 occurrences per 200,000 work hours, and the lost workday case rate was 0.52. This performance continues to be due, in large part, to the people and processes URS and CH2M HILL, the parent companies of UCOR, brought to the project. Key enablers included: - Selected and deployed experienced staff in key leadership positions throughout the organization, continually re-energizing the organization with new leaders - Implemented previously successful safety programs and initiatives from other DOE sites, such as DOE's Voluntary Protection Program - Brought fresh thinking and innovation to tackling tough project issues, such as the deactivation of the Technetium-99-contaminated areas of K-27, applying lessons learned from the D and D of K-25; and implementing a -waste factory- approach to cleanup - Maintained continuing alignment between UCOR's contract with DOE and its Performance Measurement Baseline - rapidly addressing contract changes when they arose - Maintained a readiness both from a process as well as experienced personnel perspective to support DOE OREM in performing other significant Oak Ridge Reservation cleanup activities. (authors)

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DOE OSTI2015

Nevada national security site environmental remediation Large-Scale Multi-Well Aquifer Tests Used to Define Flow Systems - 15589

Over the past 5 years, 10 new groundwater wells have been drilled and hydraulically tested on Pahute Mesa Corrective Action Unit (CAU) under the Underground Test Area (UGTA) Activity at the Nevada National Security Site (NNSS). The new wells were drilled as part of a Phase II Corrective Action Investigation to gain a better understanding of the geology and hydrology of the system and to support development of a groundwater flow and transport model used for forecasting contaminant boundaries. Multi-well aquifer testing provides the most integrated assessment of hydraulic properties and connectivity within complex geologic systems. By providing hydraulic connectivity, these tests can be used to generate insight on potential contaminant flow paths and provide constraint on overall groundwater flow pathways. Drawdown in observation wells provides direct evidence of a hydraulic connection. During well drilling and testing activities, a total of 20 aquifer tests were conducted with as many as 36 individual completion zones. A signal-processing method developed by the U.S. Geological Survey was used to improve pumping drawdown detection. Using this approach, drawdown as far away as 3-4 kilometers has been detected. In addition to the typical analysis for hydraulic property values, the observed hydraulic connectivity are qualitatively and quantitatively used to inform the hydrogeologic framework model which is updated using other permissible geologic interpretations, when necessary, to incorporate the aquifer-testing results. These results will be used for developing and building confidence in the conceptual and numerical models for the Pahute Mesa CAU. (authors)

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DOE OSTI2015

Progress updates for the Hanford waste treatment and immobilization plant project - 15593

The Waste Treatment and Immobilization Plant (WTP) Project is vital to the U.S. Department of Energy's (DOE) mission to clean up radioactive waste at the Hanford Site in southeastern Washington State. The overall WTP Project objective is to design, build, and commission the facilities and systems that will treat and immobilize approximately 211 983 m{sup 3} (56 million gallons) of radioactive waste stored in 177 underground storage tanks. The combination of technologies in the WTP makes it a first-of-a-kind facility at a scale larger than ever built for radioactive waste processing. In recent years, the project has encountered issues that affected project design completion, especially in the Pretreatment and High-Level Waste Facilities. These included technical issues, changes in requirements, changes in funding, weaknesses in the nuclear supply chain, identification of new hazards, and new information about the tank waste. The combination of these issues led to a suspension of construction of the Pretreatment Facility and a partial suspension of construction of the High-Level Waste Facility in mid-2012. Since then, the WTP Project has made significant progress in establishing and implementing a strategy for resolving these issues. This strategy focuses on resuming full production work in a sequence that fully supports the DOE plan for a phased approach for starting treatment of the Hanford tank waste, beginning with the low-activity waste streams. Concurrent with the technical and programmatic issues, the DOE Office of River Protection has made numerous changes in the processes it uses to manage and oversee the WTP Project. These changes have had a beneficial impact on the progress the project has made in establishing a path forward for resuming production activities, and on planning for the necessary contract and baseline changes needed to complete the project. (authors)

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DOE OSTI2015

Management of multiple groundwater contaminant plumes extending beyond property boundaries at the young - Rainey STAR Center (Science, Technology, and Research Center) - 15623

The US DOE Pinellas Plant-now known as the Young - Rainey STAR Center, located in Largo, Florida-manufactured components for nuclear weapons from 1956 to 1995. During decades of operations, chlorinated solvents were released from a drum storage area and from underground piping at multiple points adjacent to and beneath a 4.5-hectare (11-acre) building. Two groundwater contaminant plumes associated with contaminant sources beneath the building have been identified, delineated, and are being monitored. During a focused delineation campaign in 2008 to better define the plume boundaries prior to municipal construction projects in the area, the plumes were determined to extend beyond the site boundaries, beneath the adjacent roadway easements, and beneath four adjacent privately owned properties. US DOE has performed a number of activities in response to the discovery of the offsite contaminant plumes, including performing a high-resolution delineation of contaminant plumes; coordinating with local municipalities to complete two linear construction projects requiring dewatering in the vicinity of the plumes; performing risk assessment, risk management, risk communication, and community relations tasks associated with the project; coordinating with state regulators to identify a risk-based corrective action regulatory approach; and coordinating with impacted property owners to develop and implement institutional controls. During the replacement of a 1.2-meter (48-inch) municipal potable water line directly over the contaminant plume area, US DOE (1) constructed infrastructure to receive and treat dewatering effluent at a rate of 20 gallons per minute around the clock for 6 weeks, and (2) conducted breathing-zone air monitoring during excavation of a 3.0-meter (10-foot) deep trench. This degree of diligence was necessary to ensure and document that no site workers were exposed to chlorinated solvent vapors during the construction process, and that a large volume of potentially contaminated groundwater was properly treated and dispositioned. US DOE also took aggressive actions to pro-actively address claims regarding loss of property value on two properties associated with the groundwater contamination, which resulted in a teaming arrangement with each party for future management of the ongoing corrective actions. (authors)

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DOE OSTI2015

Modeling and Quantitative Assessment of Green and Sustainable Remediation Options for the M1 Air Stripper System at DOE SRS - 15660

The effectiveness of remediation systems needs to be reviewed periodically to assess their performance over the years relative to efficiency and effectiveness. New technologies and Best Management Practices have emerged that can improve existing remediation systems. From a Green and Sustainable Remediation analysis, the higher energy and/or water usage of older systems might not be justified from an environmental protection rationale. For example, remediation systems can run intermittently and with slower flow rates, use less power, and still provide the required level of environmental remediation and protection. This research by the Applied Research Center at Florida International University (FIU) is the preliminary phase of a Green and Sustainable Remediation (GSR) analysis of the operations of the M1 air stripper and the A/M Area groundwater remediation system at the Savannah River Site (SRS). An initial baseline analysis has helped identify opportunities for implementing Green and Sustainable Remediation (GSR) practices while maintaining the hydraulic containment and effectiveness of the remediation system. This study included the collection of contaminant recovery data from SRS reports into a database of trichloroethene (TCE) and tetrachloroethene (PCE) removal from contaminant recovery wells RWM-1 through RWM-12. Presented below are data and preliminary findings from these recovery wells. Findings show that 7 of 12 recovery wells have transitioned to more PCE removal than TCE removal; the nearby steam injection remediation of 'Dynamic Underground Stripping' mobilized DNAPL and resulted in increased recovery in nearby wells. (authors)

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DOE OSTI2015

Residual waste detection in HLW tanks - 15701

This research uses commercial sonar technology to monitor residual waste in the U.S. Department of Energy's (DOE) Hanford Site high-level-waste staging tanks, with primary focus on the detection and imaging of the settled solids at specified areas of interest along the tank surface within a limited amount of time. High-level waste (HLW) is generated at the US-DOE Hanford Site as a by-product from the processing of nuclear materials. Waste is currently stored in 177 underground carbon-steel waste tanks. Pulse jet mixers (PJM) are often used to break loose and suspend the solids that have settled at the bottom of the tanks. A typical tank can have 6-8 pulse tubes. The Solid Liquid Interface Monitor (SLIM) must be capable of measuring dynamic movements in Region 1 zone between each PJM cycle. SLIM was originally developed to map the sludge/supernate interface within the U.S. DOE Hanford Site's HLW tanks. SLIM is a dual-axis mechanically rotating sonar and consists of an acoustic transducer, rotation motor with gearbox, tilt motor, position reference sensor, and pressure balancing mechanisms and its associated deployment platform. The sonar gathers a swath of data in the horizontal plane and rotates the transducer through a programmed angle around the vertical axis. Oil-filled device. No user serviceable parts. No semiconductors. Hard anodized aluminum and polyurethane delrin. May be deployed in areas of significant radioactivity. Kaolin will be used during mixing operations in order to simulate the physical properties of the expected slurry. In order to reduce the amount of time needed to image and object, all settings were decreased to their minimal state. The low resolution settings provide insufficient data for the manufacturer's 3D profiler to compile a visible point cloud and much less to allow the meshing algorithm to work properly. Several filtering algorithms have been applied to each scan in order to remove erroneous spikes and ghosting effects. Data has been collected for the mixing process of kaolin. This data consists of scans executed while the pump was active and inactive. The imaging algorithm has also been used with data derived from scans of 3% or less of kaolin. Future work: Mixing of kaolin within an experimental tank will be conducted in order to simulate the settling time of the HLW within the tank. The same filtering algorithms will be applied to each of these scans to evaluate the SLIM's efficiency to image solids at the bottom of a tank through increasing volume of kaolin.

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DOE OSTI2015

Quantitative assessment of sustainable remediation options for the M-1 air stripper system at SRS - 15702

The US Department of Energy (DOE) Savannah River Site (SRS) covers 310 sq. miles and is located south of Aiken, SC. The site produced materials used in the production of nuclear weapons from the 1950's to the 1980's. Trichloroethylene (TCE) and tetrachloroethylene (PCE) were the main solvents used in degreasing and other industrial operations. These solvents are categorized as dense non-aqueous phase liquids (DNAPLs), semi-volatile, and hazardous chemical compounds. In the 1980's, operations were initiated to remediate the contaminated soil and groundwater which continues today. The M-1 air stripper and well network has operated continuously since 1985 at an average electrical load of 150 kW and flow rate of 420 gpm. The influent TCE concentration to the air stripper has decreased exponentially from 25,200 ug/L in 1986 to 2,230 ug/L by the end of 2012, with the same energy consumption and water pumping rate. To analyze the operation of the SRS A/M Area groundwater remediation system using state-of-the-art modeling tools to provide suggested engineering and operational improvements to expend less resources while still containing the contaminant plume. Implementation of improvements will help DOE-EM apply sustainable remediation at its sites and help DOE achieve DOE-wide sustainability performance metrics. Located in the northern part of SRS within the lower reaches of the Tims Branch watershed (topographic elevation from ∼420 X to ∼ 118 X). Consists of facilities that fabricated reactor fuel and target assemblies (M-Area), and administrative and support facilities (A-Area). M-1 Air Stripper and Recovery Well Network Installed in 1985 to treat groundwater in order to reduce chlorinated solvent concentrations. 17 recovery wells have been installed over the years. Currently recovery wells 1-12 feed the M1 air stripper. The treated groundwater is discharged to a stream in Tims Branch. The monthly removal rate and the cumulative mass removed for TCE and PCE in the 12 recovery wells was analyzed for 1985-2012. 7 of 12 recovery wells have transitioned to more PCE than TCE removed. This is an expected result since TCE was initially used and then replaced by PCE. The rate of recovery in some wells was affected by the Dynamic Underground Stripping process. 7 wells exhibit exponential decay in contaminant removal while 5 exhibit steady concentrations, and 2 exhibit linear decreases. Future Work: Identify opportunities to improve efficiencies related to electrical energy, water usage, and the use of other resources, beginning with mechanical design modifications. Investigate operational strategies to increase system performance by optimizing the hydraulic loads, pumping rates, contaminant mass flow rates and well drawdown levels. Determine a set of metrics which will correlate the pumping rates, the cone of depression, and the interaction between the wells with the contaminant mass flow rates.

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DOE OSTI2016

Waste Treatment and Immobilization Plant, a Leader in the International Glass Community - 16003

The U.S. Department of Energy (DOE), Office of River Protection (ORP) is constructing the Tank Waste Treatment and Immobilization Plant (WTP) [1] to treat radioactive waste currently stored in underground tanks at the Hanford Site in Washington State. The WTP that is being designed to separate the tank waste into high-level waste (HLW) and low-activity waste (LAW) fractions with the majority of the mass (approximately 90 percent) directed to LAW and most of the activity (greater than 95 percent) directed to HLW. The pretreatment process, envisioned in the baseline, involves the dissolution of aluminum bearing solids to allow the aluminum salts to be processed through the cesium ion exchange and report to the LAW Facility. There is an oxidative leaching process to affect a similar outcome for chromium-bearing wastes. These two unit operations were advanced to accommodate shortcomings in glass formulation for HLW inventories. A significant consideration to the most recent revision of the glass models is the extensive collaboration developed, funded, managed, and coordinated from the ORP. The current effort includes researchers at the Pacific Northwest National Laboratory, Idaho National Laboratory, Savannah River National Laboratory, Brookhaven National Laboratory, Catholic University of America, Washington State University, Rutgers University, Institute of Chemical Technology Prague, University of Ottawa, Tokyo Institute of Technology, The University of Adelaide, and University of Sheffield. Independent technical evaluation having been solicited from faculty of Alfred University and Vanderbilt University. These advances in glass chemistry generate a need to revisit the feed vectors, flowsheet, and the unit operations driven by minimal waste loading requirements set forth in the contract for the design and construction of the plant. The current status and plans for the immediate future of glass chemistry are the subject of the primary concern to successfully completing our clean-up mission at Hanford. (authors)

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DOE OSTI2016

Cigeo, The French Geological Disposal Facility Project: Preliminary Design (APS) Phase - 16038

The Cigeo project has been in the works for 25 years. Numerous studies have been conducted, increasingly associated with the Meuse/Haute-Marne site, with further specific research thanks to direct access to the Callovo-Oxfordian clay formation from the underground laboratory of Bure-Saudron. These studies and research initially aimed to demonstrate the feasibility of the repository. They also helped gain a high level of understanding of phenomena to support design studies and demonstrate safety. Transition to the industrial phase began with the development of a plan for delivering waste to the facility for disposal. The plan introduced sequencing for the various types of waste to be disposed of, and was optimised to determine the size of inspection, transfer and handling facilities. In describing the life of the repository and therefore the vision for its operation, it has become obvious that our generation should not impose choices on future generations. We must provide them with reference technical solutions, with the financial resources to implement them. It is also our duty to begin the construction and initial operating phases. However, because the facility will operate over several generations, we must leave a degree of flexibility so that they may reassess the options that we define and adopt their own solutions, as necessary. They will also benefit from operational experience gathered as facility operations develop. This is the context in which the preliminary design phase is being finalised in preparation for the detailed design phase, with the aim of gradual commissioning during the latter part of the next decade. (authors)

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