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All sourcesNASA NTRSDOE OSTI
DOE OSTI2023

Plasma field faraday cage system

A system for creating a plasma field Faraday cage around a structure, the system comprising a plurality of lasers spaced apart from each other, each laser being configured to transmit an electromagnetic energy beam to a focal point of an atmosphere region, each electromagnetic energy beam having an amount of energy less than an amount of energy required to ionize air, the electromagnetic energy beams intersecting at the focal point such that the electromagnetic energy beams cooperatively ionize the air at the focal point to block electromagnetic radiation from passing through the focal point.

Timpson, Erik Joseph↗
DOE OSTI2017

Probabilistic Performance Assessment for Deep Borehole Disposal of Cs/Sr Capsules - 17143

The US Department of Energy (DOE) performed an assessment of disposal options for spent nuclear fuel (SNF) and high-level radioactive waste (HLW) that recommended the consideration of deep borehole disposal (DBD) of smaller DOE-managed waste forms, such as cesium (Cs) and strontium (Sr) capsules. To further assess the safety and viability of the DBD concept, post-closure performance assessment (PA) analyses were performed for DBD of Cs/Sr capsules. The post-closure PA included a reference design concept for Cs/Sr capsule disposal, feature, event, and process (FEP) analysis, scenario development, and modeling using the PFLOTRAN code. PA simulations were run for both nominal and disturbed scenarios for long-term radionuclide transport away from the deep disposal borehole. The nominal (expected) post-closure release scenario included FEPs for short-duration (a few hundred years) thermally-induced upward fluid flux through the borehole seals and/or disturbed rock zone (DRZ) followed by longer-term slow diffusive transport. Simulations included a baseline deterministic run and a set of probabilistic realizations (using Latin Hypercube Sampling (LHS) from parameter distributions) to examine the sensitivity and importance of the long-term radionuclide transport to processes and parameters such as: waste package durability; seal porosity and permeability, disturbed rock zone (DRZ) porosity and permeability; and radionuclide sorption in the seal materials, DRZ, and crystalline host rock. The disturbed scenario included a waste package 'stuck' in the crystalline basement above the emplacement zone near a hypothetical borehole-intersecting fracture. Simulations included two deterministic runs to examine the sensitivity to the regional head gradient. The nominal and disturbed scenario PA results suggest that a favorable safety case can be developed for DBD of Cs/Sr capsules and helped to identify key areas of uncertainty, which in turn can inform future DBD research and development (R and D) activities, including a field demonstration project. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2023

Biofuel Air Emissions Analysis

U.S. has goals to produce 3 billion gallons of sustainable aviation fuel (SAF) annually by 2030, increasing to 35 billion gallons by 2050 to decarbonize the aviation sector. Meeting these production targets will require large number of biorefineries to be set up. However, ability to comply with federal air quality standards is prerequisite to being issued a construction permit. Negotiating the permitting process for a new biorefinery can be quite onerous and cost the investors significant time and money. Although there can be numerous reasons for delayed biorefinery construction, air permitting is fraught with pitfalls because the permitting process relies on precedence, which the future SAF biorefineries lack. NREL's Biofuel Air Emissions Analysis project is unique and innovative in terms of the tools, approaches, and analyses provided. NREL is the only national laboratory that is actively working at the intersection of Federal air quality regulations, emissions and air quality analysis across the supply chain, and process design. This project is focused on providing much needed data and analyses that address biorefinery air permitting. This project develops models and quantitative analyses and measures progress towards meeting air quality regulatory requirements. These models and methods are applied to analyze air permitting related to wastewater sludge to biofuel conversion pathways using hydrothermal liquefaction (HTL), impacts of HTL pathway on local and regional air quality including an assessment of health and equity impacts. In addition to filling research gaps, this project also disseminates the findings to the relevant stakeholders at BETO, other national labs, and regulatory agencies.

air quality↗
DOE OSTI2015

Niagara Falls Storage Site - Balance of plant investigation results - 15432

The Niagara Falls Storage Site (NFSS) is a 77.3-hectare (ha) (191-acre) property that is owned by the United States Government and located in the township of Lewiston, Niagara County, New York. The NFSS is part of the former Lake Ontario Ordnance Works (LOOW) that was used by the War Department beginning in 1942 for the production of trinitrotoluene (TNT). During the 1940's and 1950's, the Manhattan Engineer District and the Atomic Energy Commission brought various radioactive wastes and uranium processing byproducts (residues) resulting from our nation's atomic energy program to the LOOW for storage. Site operations caused soil, sediment, and groundwater contamination that lead to several remedial actions, which culminated in the construction of the Interim Waste Containment Structure (IWCS) on the NFSS. The U. S. Army Corps of Engineers (USACE)-Buffalo District is the lead Federal agency for Formerly Utilized Sites Remedial Action Program (FUSRAP) remediation of the NFSS. As the lead agency, USACE is conducting a remedial investigation/feasibility study (RI/FS) pursuant to the protocols set forth in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). CERCLA activities at the NFSS have transitioned from the site RI activities to the FS evaluation of potential remediation alternatives. USACE recognizes the need to implement a focused CERCLA FS process and, therefore, has established three separate operable units (OUs) for NFSS: the IWCS OU, the Balance of Plant (BOP) OU [i.e., all on-site areas outside the boundary of the IWCS], and the Groundwater OU. This paper details recent investigations into the underground utilities, groundwater/soil contamination, and past storage of contaminated material on the Balance of Plant Operable Unit of the NFSS. Recent fieldwork activities have investigated areas of elevated groundwater contamination as well as an investigation to determine/eliminate any preferential pathway that historical underground utilities may have provided on-site in these areas. Additional areas of investigation included strategic placement of groundwater wells at locations of historic residue storage piles and intersections of various underground utilities (based on aerial photography and geophysical surveys). Several hundred locations across the site were investigated with a gamma walk-over survey, boring, surveying and sampling of soil-cores to aide in the delineation of soil contamination throughout the Balance of Plant Operable Unit. The series of investigations indicated multiple operational areas still have impacts above background conditions, risk-based concentrations, and promulgated maximum contaminant levels for multiple media in the Balance of Plant Operable Unit. The soil, groundwater, sediment, and utility sampling data show that 1) radionuclide impacts derived from ore-residue handling operations still exist, 2) impacts from other inorganic and organic compound exist in TNT manufacturing and support areas, and 3) contaminant transport from past source areas is minimal. The full compendium of site history and recent sampling data provides a well-defined conceptual site model that provides the necessary input data to prepare volumetric soil estimates for the Balance of Plant Operable Unit Feasibility Study. The scale of the NFSS and complexity of prior operations provide many remedial challenges. (authors)

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

The Enhanced Sealing Project, Monitoring a Full-Scale Shaft Seal at Canada's Underground Research Laboratory (2009-2015) - 16070

A full-scale shaft seal was designed and installed in the 5-m-diameter main shaft at Canada's Underground Research Laboratory (URL) in 2009. Located where the main shaft intersects a water-bearing fracture zone at a depth of approximately 273 m, a 6-m-thick clay component was sandwiched between two 3-m-thick concrete components. The clay component was 40:60 mixture of bentonite and quartz/feldspar sand and spans approximately 1 m beyond the maximum identified vertical extent of the fracture zone. Its purpose is to limit the mixing of saline groundwater from the deeper region with the fresher, near-surface groundwater. Its construction was part of Canada's Nuclear Legacy Liabilities Program (NLLP). The 1. phase of the Enhanced Sealing Project (ESP), a jointly-funded Research, Development and Demonstration (RD and D) project was started in 2009 to monitor the saturation of the shaft seal until the end of 2013. The 2. phase, extended monitoring of the ESP is supported by Posiva (Finland), Andra (France) and CNL (Canada) and this will run until the end of 2016. The slow evolution of the seal and its surroundings and complete removal of the surface facilities at the URL site in 2014, has meant that the ESP monitoring has evolved to a stand-alone, lower frequency data collection program. Information gained from the ESP monitoring is applicable to support the development of sealing technology to safely close a deep geological repository for the permanent disposal of radioactive wastes. (authors)

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

Directional Drilling Technology for HLW Disposal - Outline of System and its Application - 16078

During high-level waste (HLW) disposal site selection, borehole measurement and logging to investigate the hydro-geological and geo-mechanical conditions of the host rocks is a very important way to examine the potential of the disposal candidates. In Japan, attention is being given to Neogene soft sedimentary rock as the host rock for HLW disposal. In particular, the soft sedimentary rock in coastal areas is thought to be one of the best candidates, because there is little driving force from underground water. Directional drilling is supposed to be efficient under limited topographic and geological conditions, and the Central Research Institute of Electric Power Industry (CRIEPI) has been conducting a project on directional drilling and logging/measurement technologies since 2000. Basic directional drilling system was developed and the system was applied to the Neogene normal sedimentary rock at the Hokushin area of the Horonobe town in Hokkaido. The borehole was drilled to the 700 m long and the applicability of the system was confirmed until 2004. A basic directional drilling system was developed, and the system was applied to the Neogene normal sedimentary rock in the Hokushin area, in the town of Horonobe in Hokkaido. A 700-m borehole was drilled, and the applicability of the system was confirmed in 2004. After conducting a seismic reflection survey for the Omagari fault distribution at the Kami-Horonobe area in the town of Horonobe, a drilling site was selected, and a borehole trace was planned to perpendicularly intersect the fault zone in 2005. Considering the planned trace, a 1000-m-long borehole was drilled to a depth of 450 m. From 750 m to the bottom (1000 m), the borehole was horizontal. The total core recovery was 99.8%, even though it was drilled in the fault zone. The geological, hydrological, geo-mechanical, geophysical, and geochemical data were collected using borehole logging/measurement/survey and core logging/measurement/analysis, and the Omagari fault was characterized. After conducting all the work in the borehole, a steel pipe was inserted into the borehole to case the wall. Open hole sections for monitoring were constructed considering the hydro-geological conditions throughout the hole. Then, the monitoring system was inserted and set up to obtain the initial conditions of the groundwater pressure and chemistry. (authors)

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

Directional Drilling Technology for HLW Disposal - Long Term Monitoring in the Borehole - 16079

Central Research Institute of Electric Power Industry (CRIEPI) has been conducting a project for the directional drilling and measurement/logging technologies to survey hydro-geological condition at the stage of the preliminary investigation (PI) of site selection for the deep geological disposal of HLW. 1000 m length borehole which intersects the Omagari fault was drilled by directional drilling technology in order to verify the drilling technology in Hokkaido. Long term monitoring to clarify pore water pressure and water chemistry in the drilled borehole was also developed. We set measurement intervals on a hanging wall side of a main fracture and started the measurement of pore water pressure in February 2014. We assume that long term monitoring for several boreholes will be achieved in vast areas where power supply and/or communication networks are not available at the PI stage. Thus, we have been developing an automatic data acquisition system for long term monitoring, which enables us to access data remotely. The monitoring system, which was set in Horonobe-town in Hokkaido, is an automatic data acquisition system that performs long term monitoring of pore water pressure. This paper provides an overview of the development of monitoring technologies of pore water pressure measurement in the borehole as well as the automatic data acquisition system. (authors)

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

Treatment of Chlorinated Solvents in Groundwater Beneath an Occupied Building at The Young - Rainey STAR Center (Science, Technology, and Research Center) - 16342

Groundwater contamination, consisting of two dissolved-phase plumes originating from chlorinated solvent source areas, in the southeastern portion of the Young- Rainey Star Center (also known as the Pinellas County, Florida, Site) in Largo, Florida, has migrated beyond the property boundary, beneath the roadways, and beneath adjacent properties to the south and east. Groundwater contamination will persist as long as the onsite contaminant source remains. The origin of the contamination appears to be multiple long-term point sources beneath Building 100, a 4.5 ha (11 acre) building that housed manufacturing facilities during US DOE operations at the site. The site is now owned by Pinellas County, and most of the space inside the building is leased to private companies, so DOE chose not to conduct characterization or remediation through the floor of the building, instead choosing to conduct all work from outside the building. Injection of emulsified soybean oil and a microbial culture has been used at other areas of the site to accelerate naturally occurring bacterial processes that degrade groundwater contaminants to harmless compounds, and that same approach was chosen for this task. The technical approach consisted of installing horizontal wells from outside the building footprint, extending through and around the identified subsurface treatment areas, and terminating beneath the building. Two 107 m (350 ft) long wells, two 122 m (400 ft) long wells, and four 137 m (450 ft) long wells have been installed to intersect the inferred source areas and confirmed contaminant plumes beneath the building. DOE then injected emulsified vegetable oil and a microbial culture into the horizontal wells at each of several target areas beneath the building where the highest groundwater contaminant concentrations have been detected. The target areas are the northwest corner of the building between the old drum storage pad locations and monitoring well PIN12-S35B, the vicinity of former monitoring well PIN12-S57B, and hydraulically up-gradient from the south plume and the east plume at the points where they exit from beneath the building. We describe the details of designing and constructing horizontal injection wells for bioremediation beneath a large, occupied industrial production facility, including lessons learned; technical, logistical, and environmental challenges; community relations; and regulatory relations. Because of the expected lag in biological acclimation and response, distance between the treatment areas and associated monitoring points, and low groundwater velocity, it will likely be years before the full impact of the project will be realized. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2023

Laser ablation sampling system and method

A method and system for sampling a solid sample material can include the step of mounting the sample material on a support. A sample surface is coated with a surface treatment composition in a dry deposition process. A solvent supply conduit for supplying solvent to the sample surface and a solvent exhaust conduit for withdrawing solvent from the sample surface can be provided. Solvent is flowed from the solvent supply conduit to the surface treatment composition and the sample surface such that the solvent contacts the surface treatment composition. A laser beam is directed from a laser source to the sample and the surface treatment composition. The laser beam will ablate the sample and the surface treatment composition in portions intersected by the laser beam. Ablated sample material enters the solvent liquid and will be transported with the solvent away from the sample surface through the solvent exhaust conduit.

Kertesz, Vilmos↗
DOE OSTI2016

An Efficient Sampling-Based Method for Sensitivity and Uncertainty Analysis Through RAVEN

Sensitivity analysis (SA) and uncertainty quantification (UQ) are now widely recognized as essential parts of analyses for complex nuclear systems. Plenty of well-established methodologies are already available for performing SA and UQ, such as Monte Carlo analysis, adjoint-based method, and variance decomposition. The focus of this summary is on developing an efficient sampling-based approach to perform SA and UQ through RAVEN. RAVEN (Risk Analysis and Virtual control Environment) is a software framework able to perform SA and UQ, currently under development at the Idaho National Laboratory. In literature, a number of approaches have been developed to accelerate the process of SA and UQ for large complex systems, such as principal component analysis (PCA) of input space, input-output correlation analysis, and intersection subspace methods. The fundamental idea is to identify the dominant active directions in the parameter space prior to conducting SA and UQ. The premise is that the number of active directions is much less than the dimensionality of input space. In this work, the PCA or Karhunen-Loeve expansion or SVD method is implemented in RAVEN to identify the active directions. This approach is also combined with the forward sampling approaches, such as Monte Carlo, Grid, Latin Hypercube, and Response Surface Design sampling approaches that are currently available in RAVEN, to perform SA and UQ more efficiently. The summary is organized as follows. In the following section, we present the PCA-based forward sampling approach. The effectiveness and efficiency are discussed in the numerical results section. The paper then ends with a concluding summary. In this summary, we have presented PCA-based forward sampling approach to perform SA and UQ. The goal is to reduce the computational overhead for repetitive executions of complex nuclear systems that are generally required when performing SA and UQ. The control of correlations between input parameters is implemented in RAVEN to better represent the input relationships. In addition, we are currently examining our implementations with more realistic models, and we are also focusing on implementation of some new high-dimensional input reduction techniques in RAVEN. (authors)

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2016

The Solid Angle for a Spherical Surface Source and a Detector with an Arbitrary Aperture: An Elegant Proof

It has previously been proven that the solid angle (or geometry factor, also called the geometrical efficiency) for a spherically symmetric outward-directed surface source with an arbitrary radius and polar angle distribution and an arbitrary detector aperture is equal to the solid angle for an isotropic point source located at the center of the spherical surface source and the same detector aperture. The solid angle for a source-detector system is the fraction of source particles that enter the detector aperture and so it is not purely geometric-the angular distribution of the source is a factor. The previous proof relied on an analytic transport-theory (streaming only) calculation of the solid angle Ω for a spherically symmetric surface source and a point detector. In this paper, a new, more elegant proof is given. Since the net current across any portion of a plane that intersects the center of a spherical surface source is zero, the solid angle for a spherical surface source with any polar angle distribution and a uniform azimuthal angle distribution and any detector aperture is equal to the solid angle for an isotropic point source and the same detector. This insight obviates the calculus and trigonometry involved in the previous proof. (author)

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2019

Value Based Decision Approach to Help Inform Waste Management Guidance for VLLW Following an RDD Detonation - 19510

The detonation of a radiological dispersal device in an urban environment or similar large-scale radiological event has the potential to spread radioactive contamination over a large area. The resulting effort to clean up and dispose of this waste will involve input and coordination from a wide variety of stakeholder groups, especially if the waste crosses municipal and state boundaries. Guidance designed to help effectively and safely deal with the wastes generated from incident cleanup will need to navigate the intersection of stakeholders at the local, regional, and national levels. At the same time, the sheer size of such a cleanup effort and the volumes of wastes generated will require innovative and potentially novel solutions compared to current Low-Level Radioactive Waste disposal practices. A structured decision-making approach incorporating value-focused thinking is one method that could be employed to help build stakeholder confidence in a given cleanup guidance strategy and documentation. This approach would help ensure that all stakeholder perspectives were accounted for in a given decision situation and to promote transparency in the decision-making process. This paper will discuss research into the role and development of a public stakeholder tool used to gather input from relevant stakeholders in order to help inform cleanup and disposal guidance of Very Low-Level Radioactive Waste following a radiological disaster. This tool is being designed to draw on aspects of value-focused decision making. Case studies from two prominent recent events will be discussed to illustrate some of the key issues that could benefit from such an approach to stakeholders. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Erosion Challenges at the L-Bar Disposal Site - 19561

The L-Bar, New Mexico, Disposal Site is located in the northeast corner of Cibola County, 10 miles north of Laguna, and was the former site of a uranium mill and underground mine. The mill operated from 1977 to 1981 where a total of 1.9 x 10{sup 6} tonnes (2.1 million tons) of ore was processed. Solid and liquid byproduct, or tailings, from the milling process were impounded behind a dam constructed of native weathered Mancos Shale, which is a predominant geologic formation in the area. The tailings were encapsulated in place, and the resulting 40.5-hectare (100-acre) engineered disposal cell was completed in 2000. The 299-hectare (738-acre) Uranium Mill Tailings Radiation Control Act Title II site was transferred to the US Department of Energy (DOE) Office of Legacy Management under a US Nuclear Regulatory Commission general license in 2004. During reclamation activities, channels were designed and constructed into the surrounding weathered shale to protect the disposal cell from high-precipitation events. Due to the highly erodible soils and anticipated sediment deposition into the diversion channels, a sediment trap was also excavated. By excavating the channels and sediment trap, the local base elevation was altered, which exacerbated erosional forces. Recontouring surrounding drainage basins during the reclamation activities also promoted erosion by reducing natural rock armoring and vegetation that aids in soil stability. To compound the erosion issue, the L-Bar site is susceptible to short-duration, high-intensity, localized convective storms. Because the local geomorphology includes soils consisting of weathered shale, these precipitation events are not conducive to absorption into the soils, but rather to sheet flows that follow topography and concentrate in lower elevation areas where flow volumes and velocities increase. These factors result in the formation of deeply incised gullies and promote soil piping, which is an important geomorphic process in the widening of arroyos and the advancement of head-cutting, evident at the L-Bar site and surrounding areas. At the first annual inspection by DOE in 2005, it was noted that extensive erosion was occurring upgradient of the sediment trap. DOE determined that the design of the site's drainage system was the cause of extensive erosion. It is believed that by lowering the base elevation of the local drainage system through excavation of the sediment trap, the geomorphic response common to fluvial systems in a semiarid environment has increased the incision and remobilization of sediment downstream. Over time, these sediments would be deposited in the channels, which are designed to divert runoff away from the disposal cell, effectively limiting their capacities. The development of alluvial fans on one side of the channel directs flows to the opposite side of the channel, presenting the risk of cutting into the side slopes of the disposal cell. In addition, the upstream migrating gullies could intersect access roads and create hazards for adjacent stakeholders, including their grazing livestock. Current estimates conclude that potential offsite impacts could occur within the next 20 years, with gully migrations of up to 19 meters (63 feet) per year. In 2009, several erosion-control structures were constructed to reduce runoff velocities and ease the elevation differential created by the construction of the sediment trap and diversion channels. The first measurable storm events after construction occurred in August and September 2011, where one structure washed out and another structure was bypassed when runoff breached an earthen berm. DOE has conducted site assessments, continues to monitor erosion, and has applied lessons learned in the process of evaluating options to repair or modify the structures to stabilize the site and prevent potential short-term damage to adjacent properties as well as long-term damage to the disposal cell. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Stability of a Uranium-Contaminated Plume in a Karst Aquifer in Northwest New Mexico - 19574

The US Department of Energy (DOE) Office of Legacy Management monitors groundwater contamination resulting from ore processing operations conducted between 1953 and 1982 at a former uranium mill site on property that is now part of the Bluewater, New Mexico, Disposal Site. The site is located in the Grants Mineral Belt in northwest New Mexico at the base of the Zuni Mountains. It is estimated that prior to mill tailings encapsulation in 1995, approximately 21.6 billion liters (5.7 billion gallons) of tailings fluid seeped from the main tailings impoundment into the underlying aquifers. Today, there is remnant groundwater contamination from the mill in two aquifers: the San Andres-Glorieta (SAG) bedrock aquifer and the Ancestral Rio San Jose alluvial aquifer. Groundwater contamination in the SAG aquifer is of particular concern, as the aquifer is the primary water source in the region for municipal, agricultural, and industrial use. Municipal wells for the region are located as close as 6.4 kilometers (4 miles) southeast of the Main Tailings Disposal Cell. The SAG uranium plume extends east for more than 4.8 kilometers (3 miles) beyond the site's eastern boundary, along the direction of groundwater flow. The plume intersects the Homestake Mining Company site, another former uranium mill site undergoing active remediation. The SAG aquifer contains two formations, the Lower Permian San Andres Limestone and the Glorieta Sandstone. Most of the groundwater moving through the SAG aquifer is in ancient karst features consisting of open conduits where the limestone has dissolved, resulting in flow through solution cavities, solution channels, cavernous zones, and enlarged fracture openings. These features make the San Andres Limestone extremely permeable and capable of rapidly transporting groundwater. In addition, the karst characteristics make the aquifer difficult to evaluate and the uranium plume difficult to characterize. Numerous faults in the area, including two directly under the Main Tailings Disposal Cell, further complicate characterization by impacting groundwater flow both onsite and in the vicinity. A DOE study of the SAG aquifer uranium plume at the Bluewater site, conducted in 2014, indicated that the plume had moved offsite soon after the start of milling and effectively stabilized in its present location prior to the 1980's. An updated study completed in 2018 confirmed previous information regarding general plume stability and provided insight regarding potential localized trends east and south of the Main Tailings Disposal Cell. One such trend may be decreasing uranium concentrations east of the Main Tailings Disposal Cell, potentially attributable to regional groundwater elevation decreases. Both the 2013 and 2017 plumes suggest that the dissolved uranium contamination is derived from the leaching of a secondary mineralized zone derived from seeped tailings fluids in the geologic formations and fault zones below the Main Tailings Disposal Cell at the Bluewater site. In developing the 2013 and 2017 SAG aquifer uranium plume depictions, DOE had to address challenges associated with data quality and comparability. Analytical results used to determine the plume extent were compiled from multiple sources, including the state of New Mexico, Homestake Mining Company, and DOE. Each source used different well identifiers and coordinate systems, and well information between sources was inconsistent. Also, the integrity of some wells was questionable and necessitated review; casing integrity was found to be compromised in multiple wells. Given these uncertainties, some of these wells were excluded from the characterization. Another source of uncertainty is the paucity of wells, particularly monitoring wells, near or immediately downgradient of the leading edge of the plume. Therefore, the exact extent of the SAG aquifer uranium plume is not known at this time. There is, however, no evidence or indication of milling-related contamination in municipal wells. Furthermore, due to plume stability and direction of groundwater flow, the municipal wells are not expected to be impacted. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Leveraging Environmental Monitoring Results from Department of Energy Sites for Research on the Food-Energy-Water Nexus

The Annual Site Environmental Report (ASER) from a U.S. Department of Energy (DOE) Site summarizes environmental data; environmental management performance; compliance with applicable DOE, federal, state, and local regulations; and restoration and surveillance monitoring programs. The Savannah River Site (SRS) produces ASERs that include results of monitoring mercury levels in fish samples obtained in the vicinity of SRS. Mercury is a toxic trace metal and the methylated organic form is a neurotoxin that bioaccumulates in the food web, endangering humans and other organisms. In United States, power plants are the largest source of mercury emissions. Research Objective: To determine the patterns of mercury levels in fish samples reported in the SRS environmental monitoring reports. We developed box plot visualizations to make sense of the data as well as identify fish species, dates and location with outlier mercury content. The integration and visual representation of multi-year datasets can support decision making processes on environmental compliance and environmental sustainability conducted at U.S. DOE Sites. We are constructing datasets from textual, image and multivariable data sources in the multi-year ASERs of the U.S. DOE Savannah River Site (SRS https://www.srs.gov/general/pubs/ERsum/index.html). The Fish Surveillance for mercury presents a case study for the intersection of food, energy and water systems. The dataset of 864 records (2008 and 2009) of mercury levels includes water location of fish, fish species, collection date and mercury content of fish sample. The patterns of mercury levels in the fish species as well as locations provide knowledge for further investigations. A research area for future studies is the composition of microbial communities in fish guts of varying levels of mercury.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2020

Hanford Tank Vapors in Worker Breathing Zones - Source, Dispersion, and Receptor Data - 20373

A wide range of organic and inorganic chemicals from historical Hanford Site processes are now stored in 177 underground storage tanks at the Hanford tank farms. Workers at the Hanford tank farms have expressed concerns about chemical vapor exposures for many years. During the spring of 2014, worker reports of chemical odors and/or symptoms prompted the development of the Savannah River National Laboratory Hanford Tank Vapor Assessment Team (TVAT) and their resulting independent assessment and recommendations concerning tank farm worker reports of vapors. The Tank Vapor Assessment report included a hypothesis that 'vapors coming out of tanks in high concentration (bolus) plumes sporadically intersected with the breathing zones of workers, resulting in brief but intense exposures to some workers.' The focus of this effort is to present current knowledge to describe the mechanisms by which workers may experience short duration vapor concentrations above background in the tank farms environment. The TVAT hypothesis that workers have experienced concentrations approaching 80% of the tank headspace up to 3 meters (10 feet) from tank sources is not supported by sampling data or modeling results. Modeling indicates that concentrations are quickly reduced from the source, and that the upper end of predicted concentrations at worker breathing zones are a factor of 10 or more lower than source concentrations. Area measurements corroborate the fact that worker breathing zone concentrations are 10 to 100 times lower than source concentrations, and events with elevated concentrations are rare. These reduced vapor concentration levels may result in detectable odors or irritation, depending on a worker's specific odor threshold and sensitivity to the chemical species. Short-duration vapor events may be mitigated by evaluating daily atmospheric conditions in conjunction with planned tank farm activities. Monitoring changing conditions related to tank vapors concentrations at the source and within worker breathing zone is also an important step to protect workers from short duration elevated concentration events. (authors)

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

Characterization of NORM in an Urban Environment using HPGe Measurements and MCNP6 Simulations

This work is part of a larger project aimed at producing an operationally relevant, validated simulation environment that can be used as a 'virtual testbed' for counterterrorism and counterproliferation efforts. Examples of such efforts include searches for illicit radiation sources before and during large special events, such as the presidential nominating conventions, inaugurations, and large sporting events. Once validated by laboratory and field measurements, this testbed can be used to test and validate algorithms and detector systems designed for various search missions in an urban environment. The detection of radioactive sources in a city is greatly complicated by natural background radiation, which emanates from various materials common to an urban environment, such as roadways, sidewalks, and building exteriors. The methods and results offered here represent the conclusion of an effort to characterize the concentration of naturally occurring radioactive material (NORM) in various elements in a controlled, but representative, urban environment. Some of the methods discussed in previous work will be briefly reiterated here, but more detail can be found in the preceding work. The location chosen for this effort was a Military Operations on Urban Terrain (MOUT) environment at the Fort Indiantown Gap (FTIG) National Guard training facility in Pennsylvania. This site was chosen because it replicates a small town where traffic and pedestrian access could be easily controlled, as to not interfere with the background measurements. This endeavor involved over 70 measurements using a high-purity germanium (HPGe) detector designed to ascertain the NORM concentrations in the soil, asphalt roads, gravel lots, concrete intersections, sidewalks, foundations, and walls found throughout the site. The NORM concentrations determined from this work will be incorporated into a large-scale simulation that can be used to investigate various search techniques and algorithms, detector types and setups, and to produce representative synthetic data for future work.

07 ISOTOPE AND RADIATION SOURCES↗
DOE OSTI2017

MCNP6 and SERPENT2 Performances with Unstructured Mesh Geometry

Traditionally, Monte Carlo codes model a nuclear reactor by combinatorial geometry. In this model, volume primitives (e,g, spheres, cylinders, parallelepipeds...) are combined together by Boolean operations (e.g. union, intersection, and complement) and replicated by lattice definitions to build the core geometry. Recently, high performances computing platforms allowed using unstructured mesh geometry in Monte Carlo codes. When this option is chosen, any type of core geometry can be modeled since the restriction of using volume primitives is removed. In an unstructured mesh geometry, Boolean operations and lattice definitions are not used since each volume is defined by triangular surfaces (facets). This study focuses on two Monte Carlo codes: MCNP (version 6.1.1 beta) developed at Los Alamos National Laboratory since 1957 and written in FORTRAN90, C, and C++ (267,000 total source code lines), and SERPENT (version 2.1.27) developed at VTT Technical Research Centre since 2004 and written in C (195,000 total source code lines). These two codes follow different approaches for the unstructured mesh geometry modeling: MCNP uses ABAQUS format, whereas SERPENT uses the STL format. In the STL (STereoLithographic) geometry model only the surfaces of the volume are meshed; the interior part of the volumes is not meshed. In the STL geometry model, the whole geometry is defined by the sequence of SOLID and ENDSOLID sections. Each volume of the geometry must have a SOLID and ENDSOLID section. The STL file contains no information specifying the materials of the volumes. MCNP and SERPENT can model any kind of complicated geometry using unstructured meshes. MCNP and SERPENT use the ABAQUS and STL file formats, respectively. The STL file format does not have tetrahedrons and has only triangular facets on the volumes boundary. This allows SERPENT simulations to run 10 times faster than MCNP. However, if Monte Carlo results have to be coupled to thermal-hydraulics codes, the interior of the geometry volumes must be meshed, which may reduce SERPENT performances.

97 MATHEMATICS AND COMPUTING↗