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A Comparison of Select USDOE and USEPA Risk and Dose Assessment Tools Utilized at Two FUSRAP Projects - 17388

The US Army Corps of Engineers (USACE) utilizes several computer programs and models to conduct risk and dose assessments at Formerly Utilized Sites Remedial Action Program (FUSRAP) projects. In the past, the USACE has primarily relied on the US Department of Energy (USDOE)'s Argonne National Lab (ANL) RESidual Radioactivity (RESRAD) computer code for performing dose and risk assessments involving radiological contamination in onsite soils and the US Environmental Protection Agency (USEPA) Preliminary Remediation Goal (PRG) and Dose Compliance Calculator (DCC) for radiological contamination in ground water. Recent USEPA guidance requires use of USEPA calculators for all media at National Priority List sites, which includes some FUSRAP sites. The USACE recently utilized both RESRAD and the USEPA PRG and DCC calculators in assessments at two FUSRAP projects for all media in order to evaluate differences in the models and determine adjustments to potentially resolve differences. The two projects involve soil and groundwater assessments and address typical FUSRAP contaminants such as uranium, radium, thorium and their progeny. This paper discusses differences between the models, lessons learned, and methods used to address stakeholder and other concerns regarding these assessments. The paper's discussions are useful for anyone performing risk or dose assessments for radiological contamination and especially those using RESRAD and the PRG and DCC calculators. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Challenges and Lessons Learned Performing Subsurface Investigations at a Radiologically Contaminated Site in an Urban Area - 17391

At the Formerly Utilized Sites Remedial Action Program (FUSRAP) Maywood Superfund Site (FMSS) the U.S. Army Corps of Engineers (USACE) has performed minimally intrusive (i.e. non-excavation) sub-surface investigations in soils, underneath roadways, and within buildings to generate information needed to determine whether contaminated material was present and to delineate the nature and extent. Given that thorium-232 (Th-232) contaminated material is present below various surfaces and that the current iteration of the Multi-Agency Radiation survey and Site Investigation Manual (MARSSIM) has only marginal guidance on evaluating and releasing subsurface data, survey design and implementation required detailed up front planning and post investigation analysis and reporting. This paper will discuss the approaches USACE utilized during a recent roadway investigation, some of the challenges encountered, a discussion of techniques used and results obtained, and an overall summary of pitfalls identified and lessons learned for future efforts. In order to evaluate selected areas, direct push technology was utilized in conjunction with plastic tubing to facilitate core capture and sample collection. PVC piping was inserted in each bore hole to prevent borehole collapse and facilitate downhole gamma logging. Soil samples were collected from the surface, from native material or the bottom of the boring, and from the interval or intervals which exhibited elevated downhole gamma readings, and from areas with an identifiable marker of contamination (i.e. soil discoloration) at the judgement of the field staff. Data was collected and evaluated using the approaches laid out in MARSSIM as best possible. As MARSSIM was developed to only address surface contamination, USACE, in agreement with regulators and stakeholders, utilized a 'varying plane' approach, where samples are evaluated as if on a single plane, and only the highest concentration encountered at any point is considered. Because the areas investigated were not easily cast into simple geometric shapes adhering to MARSSIM design criteria, it was important to ensure that Survey Unit design for Class 1 Survey Units were reasonable. All Class 1 SUs were contiguous survey units. Class 2 survey units were allowed to be non-contiguous provided that they are situated in close proximity to one another and share the same geology, conceptual site model, history, and radionuclide concentrations. The information contained in this paper will benefit Projects working with subsurface contamination which may require subsurface investigation and an understanding of the logistical, technological, and regulatory challenges. The ultimate outcome of this effort was the successful delineation of areas of contamination which will facilitate current utility work and guide future remediation. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Considerations and Lessons Learned from the Use of Gamma Spectroscopy Systems at FUSRAP Project Sites - 17459

This paper will discuss the application of gamma spectroscopy systems for analysis of environmental media samples for parents and daughter progeny of the Natural Uranium and Thorium Decay Series radionuclides. The concentrations and relative ratios of naturally occurring isotopes are used to confirm the presence of FUSRAP-related wastes and for understanding the associated potential dose and health risks. Focus will be given to lessons learned from the set-up and operation of onsite gamma spectroscopy laboratories used to provide stakeholders with defensible and timely results to support FUSRAP site investigations and remediation including adaptive survey design implementation, physical remediation and waste transport, and confirmatory final status survey activities. This paper focuses on the potential impacts to gamma spectroscopy measurement accuracy from the following: - Bias caused by sample matrix effects as well as use of different library reference values between performance evaluation study providers and testing laboratories; - Use of calibration sources with limited energy ranges, and; - Selection of available alternative isotopic decay reference data for the input of line energies and their intensities. These lessons learned include discussing how inter-laboratory measurement differences from blind performance evaluation samples are affected by the manufacturer's measurement method, including equilibrium assumptions; the isotope decay information source library used by the study provider and participating laboratories; and calibration source geometry/density variances from actual sample conditions. Any of these factors can significantly impact the accuracy of reported results data. Deepening the reader's understanding of the various factors that impact the accuracy, interpretation, and overall usability of gamma spectroscopy results data from laboratories will help ensure defensible decision-making and cost-effective mission implementation within FUSRAP and similar remediation programs. (authors)

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FUSRAP Maywood Site Remediation of Redstone Park, Lodi, NJ - 17534

The Formerly Utilized Sites Remedial Action Program (FUSRAP) is the U.S. government program started in 1974 to identify, investigate and clean up or control sites that became contaminated as a result of the nation's early atomic programs. FUSRAP was administered by the U.S. Department of Energy (DOE) until 1997, when it was transferred to the U.S. Army Corps of Engineers (USACE) by congressional action. Redstone Park is a 1.5-acre municipal park located in a residential neighborhood in Lodi, Bergen County, New Jersey, USA. The park is a designated vicinity property of the FUSRAP Maywood Superfund Site. This paper will summarize the FUSRAP history of the property spanning over 20 years and then focus on the construction and community relations challenges of recent FUSRAP actions at the site. All of Redstone Park except for a portion bordering a residential property was remediated under FUSRAP in 1996. This remaining portion was remediated in 1998. The 1996 remediation included some hand-digging of surface contamination around the roots of several large mature trees in the park. As part of this action, the DOE proposed alternate cleanup standards whereby subsurface contaminated soil would remain in place around the root balls of the trees and in deeper areas (greater than 1.2 meters [m]) under a large storm drain pipe (or culvert) that runs through the park. This proposal was made to preserve the natural value of the trees and to protect the drainage pipe from damage. After careful review which included an assessment of potential health hazards, the U.S. Environmental Protection Agency (EPA) approved this proposal. The Borough of Lodi also supported the proposal as a way to preserve the trees for the enjoyment of park users. In 2009, EPA conducted a mandatory Five-Year Review of the FUSRAP Maywood Site. The review identified data gaps which prevented a full assessment of remedy effectiveness at Redstone Park. The USACE reviewed all the historic soil data from the park [1] and developed a characterization plan to address those gaps. Field surveys and sampling confirmed that the material around the tree roots and under the pipe did not comply with the current FUSRAP Maywood Site unrestricted use soil cleanup criteria (an average of 5 pico Curies per gram of radium-226 and thorium-232 combined above background) as established in the site's Soils and Buildings Record of Decision [2]. As noted earlier, USACE also considered the widespread uprooting of trees in the region during Hurricane Sandy in 2012 in its re-evaluation of the earlier decision to leave the trees in the park in place. That re-evaluation concluded it was in the best interest of all stakeholders to remove the residual contamination in Redstone Park. USACE subsequently excavated the soil under and around the drainage pipe as Phase 1 of a two-phased approach to address this residual contamination. 1,116 cubic yards of soil were removed for safe offsite disposal during this action in June-July 2016. Phase 2 (removal of contaminated soil around the tree roots) began in September 2016 with expected completion by December 2016. The work was staged in two phases so as not to impact the park during the summer school vacation months when park use is heaviest. (authors)

54 ENVIRONMENTAL SCIENCES↗

Effectiveness of actinide management in fast reactors over a finite recycling period - 15123

Long-lived nuclear waste primarily consists of transuranic (TRU) isotopes. Full recycling of TRU isotopes can, in theory, lead to a reduction in repository radiotoxicity to reference levels in as little as ∼500 years provided reprocessing and fuel fabrication losses are limited. However, over a limited time frame, the radiotoxicity of the 'final' core can dominate over reprocessing losses, leading to a much lower reduction in radiotoxicity compared to that achievable at equilibrium. In this paper, the fuel cycle code ORION is used to model the recycle of light water reactor (LWR)-produced TRUs in sodium-cooled fast reactors (SFRs). With full actinide recycling, at least 6 generations of SFRs are required in a gradual phase-out of nuclear power to achieve transmutation performance approaching the theoretical equilibrium performance. Break-even SFRs are much less effective from a point of view of reducing waste radiotoxicity. Thorium (Th)-burner fuel cycles are found to result in slightly lower radiotoxicity than U-burner fuel cycles for the same number of generations. Closed break-even Th fuel cycles require ∼3 generations of operation before their waste radiotoxicity benefits result in decay to the reference level in ∼1000 years, provided that Pa is recycled. While this is a very long time frame, it is substantially better than the time frame required by other strategies. The integrated decay heat over the scenario time frame is substantially higher for break-even Th-SFRs than break-even U-SFRs as a result of much higher {sup 90}Sr production. As decay heat affects repository sizing, this weakens the argument for the Th cycle. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Assessment of defense-related uranium mines in the United States and other US DOE office of legacy management domestic and international uranium initiatives - 15335

US DOE's Office of Legacy Management (LM) has taken several initiatives to improve domestic uranium mining and milling operations in the United States and to contribute to the management of legacy uranium mining and milling sites around the world. Initiatives include completing the 2014 Report to Congress on Defense-Related Uranium Mines, managing the Title X Uranium and Thorium Program with the Office of Environmental Management, and assisting IAEA with uranium issues in member state countries. The 2014 Report to Congress identified abandoned uranium mines (AUMs) in the United States that provided uranium ore to the US Atomic Energy Commission (AEC) between 1947 and 1970. The report identified AUM locations, reclamation/remediation status, radiological risks and other hazards, costs for reclamation and remediation, and potential prioritization schemes for mine cleanup. To develop reclamation and remediation cleanup cost estimates and assess risks, AUMs were grouped into six categories by tons of uranium ore produced, ranging from Small (less than 91 metric tons [100 tons]) to Very Large (greater than 453,900 metric tons [500,000 tons]). Radiological risk was calculated using the RESRAD computer code for five exposure scenarios: offsite resident, onsite resident, occasional visitor, recreational visitor, and mine reclamation worker. Results indicate that 69 percent of the AUMs are in Colorado and Utah and 23 percent are in Arizona, Wyoming, and New Mexico; and that the majority of the AUMs (68 percent) were considered Small or Small/Medium production mines, producing less than 908 metric tons (1,000 tons) of uranium ore. Although New Mexico has fewer AUMs (247) than the other states in the Colorado Plateau region, AUMs in that state (primarily those in the Grants Mineral Belt) produced 45 percent of the 79.5 million tons of AEC-purchased uranium ore. About 50 percent of the AUMs are on public land managed by the US Bureau of Land Management; 435 AUMs are on the Navajo Nation. Risk estimates for the onsite resident scenario (plausible on tribal and non-federal land) could result in an incremental cancer risk greater than 10{sup -4}. Radon inhalation was the dominant contributor to radiological risk for the five exposure scenarios evaluated. Different state and federal agencies are conducting cleanup of some AUMs under various remedial and legal authorities. Activities constituting mine 'reclamation' may reduce radiological risks to humans to acceptable levels for many mines on federal public lands if the occasional visitor and recreational visitor exposure scenarios are assumed. Addressing physical hazards (e.g., open shafts) at mines where conditions could cause serious injuries is typically a priority of public land management agencies. At locations where mine-related groundwater contamination occurs, it is a significant contributor to cleanup costs. However, most Small and Small/Medium AUMs were likely developed above the water table, and some wet mines are located in areas where groundwater has high, naturally occurring levels of the same constituents (including radioactive elements) that are typically associated with uranium mines. LM is also administering, with the US DOE Office of Environmental Management, the Title X program, which was developed by Congress to reimburse private companies (i.e., those that held active operating licenses prior to 1978) for a portion of their reclamation costs for mill sites that processed ore sold to AEC. LM recently updated the program guidance document and established internal protocols for annually auditing companies. LM is assisting IAEA on two different initiatives: assisting developing countries with training on the basic steps to take to perform reclamation of uranium mines, and developing technical guidance and case studies related to safety and environmental assessments and post-closure management of uranium legacy sites as part of the IAEA Regulatory Supervision of Legacy Sites initiative. (authors)

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Radioactive contamination from 1920-50's at an urban site of the New York City and interim remedial action - 15630

The former Wolff-Alport Chemical Company operated at the location in densely populated urban area in Queens, New York, between 1920 to about 1954. The company imported, stored on-site and processed monazite sand ores from the Belgium Congo. The extracted refined products enriched in rare-earth metals were sold on the commercial market. The process residues, rich in thorium and its progeny, were originally disposed of directly to the city sewer line and probably on-site also. The site's buildings are currently occupied by the auto shops, corner delicatessen store, light construction company, ice maker/distributor, and two residential apartments. Preliminary site investigations found multiple areas with elevated levels of direct gamma radiation with the maximum reported rates of 22 micro-sievert/hour (2.2 milli-rem/hour) at surface level and 40 micro-sievert/hour (4 milli-rem/hour) inside sewer manhole access. The thoron (Rn-220) gas air concentration in outdoor areas was reported reaching 13.5 kBq/m{sup 3} (366 pCi/L) and the radon (Rn-222) gas air concentrations was reported exceeding 148 Bq/ m{sup 3} (4 pCi/L) in some buildings. The dose assessments indicated that, under realistic scenarios, some members of the public were likely to receive the radiation exposure from this contamination in excess of the New York City and Nuclear Regulatory Commission general public radiation dose limit of 1 milli-sievert /yr (100 milli-rem/yr). The interim remedial action was planned and conducted by the U.S. Environmental Protection Agency (U.S. EPA) Region 2 in close cooperation with the New York City and New York State in 2012-13. The purpose of the action was to take necessary interim measures to reduce annual public dose below limit of 1 milli-sievert/yr (100 milli-rem/yr) and reduce radon gas concentration levels in impacted indoor spaces below U.S. EPA Action Level for residencies of 148 Bq/ m{sup 3} (4 pCi/L). In order to achieve these goals, the following actions were taken: detailed radiological and occupancy surveys; development of realistic exposure scenarios; dose assessments; installation of the fence and gates around the 'backyard' portion of the site; vegetation removal; development and detailed assessment of the radiation shielding options; application of the multilayer radiation shielding in some buildings, portions of the sidewalk and unpaved areas; mitigation of radon/thoron gas entry point; and installation of the radon mitigation system in one of the buildings. The preliminary post-action analyses indicated that the action goal would likely be achieved. The interim remedial action was conducted in a tight urban setting; it has significantly reduced public health risk from radiation without closure of businesses that continued operating within the site perimeter. (authors)

61 RADIATION PROTECTION AND DOSIMETRY↗

Opportunities to Reuse and Recycle Redundant Radioisotopes - 16023

Sixty plus years of nuclear research and operation in the UK has produced significant quantities of nuclear material. To those involved in decommissioning a site or facility, this material represents a liability that needs to be managed and eventually disposed of. However to those in the wider nuclear industry and supply chain, the radioisotopes represent a potential resource of valuable, and in some cases irreplaceable material for future work. There is therefore an opportunity to create a win-win by identifying material that could be recycled or reused, removing it from being a liability and creating value from what is considered a waste. The UK is currently focused on the clean up of nuclear sites and the safe disposal of legacy nuclear material. Whilst the bulk of legacy material on these sites is mixed wastes in various solid and liquid forms, some of it consists of material produced for research purposes in the form of radioisotopes or exotic fuels. This has resulted in a plethora of unirradiated and irradiated materials in store across the UK including: Depleted and natural Uranium, Enriched Uranium, Mixed U/Pu oxides, Uranium carbide and mixed U/Pu carbides, Thorium as metal and oxides, Research radioisotopes. The material exists in almost every conceivable state from pure metal and oxides to solutions. Some material is well characterised and free from extraneous debris, other material is poorly characterised and contaminated with chemicals, experimental residues and sweepings. In addition, to reduce the risk and potential hazard across the UK there has also been a period of consolidation of obsolete radioactive sources from a wide variety of industrial or medical facilities to secure storage within a licensed site. The waste hierarchy is an established principle for the management of wastes, radioactive or otherwise. Its principles are set out and it gives top priority to prevention in the first place. Where waste is produced, it gives priority to preparation for re-use, then recycling before consideration for disposal as a last resort. The term wastes may only be applicable to the owner of the material where they may view the material as unwanted, unusable, or a by-product. It does not necessarily follow that the material is a waste to all potential owners. Therefore it is important to consider the potential value of material before it is considered for disposal since there is a significant and growing market for radioisotopes across the world. This paper will outline some of the opportunities in the UK for the recycle of surplus radioisotopes and orphan material. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Environmental Characterization Scans Using Sodium-Iodide Gamma Spectroscopy to Determine Ra-226 Concentration in Surface Soil - 16326

The recent natural gas drilling boom has brought heightened attention to the issue of TENORM waste management. Radioactive residues from the extraction, treatment, and purification of materials containing uranium and thorium, or their progeny, pose a public health hazard primarily in the form of ground water contamination. Hydraulic fracturing can liberate formation waters from shale; the high salinity of which can cause radium to move with the water to the surface. The disposal and handling of this water has been a subject of public controversy. For soil remediation projects, radium-226 is generally one of the radionuclides of concern due to its alpha emissions. However performing a survey scan for Ra-226 is difficult because its photon emissions are low energy and have minimal probability of emission per decay (186.2 keV, 3.3% abundance). Additionally resolving its emission from U-235 (185.7 keV, 57% abundance) with field instrumentation is not feasible. Therefore detection of Ra-226 relies on the presence and photon emissions of its progeny. This paper outlines methodology for calculating the minimum detectable concentration of Ra-226 in characterization scans using a sodium-iodide detector array coupled with a multi-channel analyzer. Using progeny ingrowth as a detection proxy requires knowing decay time in order to determine progeny emission rates. Knowledge of site history, process, and prior survey results can be key in determining an accurate decay time. However in the absence of such information in-situ measurements can be used to estimate decay time by comparing observed progeny emission ratios against established values. These values are determined using Oak Ridge National Laboratory's ORIGEN-ARP program to generate photon energy spectra for Ra-226 and its progeny at specified time intervals. Once decay time is established, the detector's minimum detectable concentration can be calculated by synthesizing the expected emission spectra and Los Alamos National Laboratory's Monte Carlo N-Particle transport code to simulate detector response. Traditionally, one of the steps in calculating a system's minimum detectable concentration is to place an appropriate button source under the detector, record the response, and then move the source by a specified increment. This process is repeated until the detector's spatial efficiency has been mapped. Due to the impracticality of performing this with Ra-226 button sources of varying decay times, Monte Carlo N-Particle transport code was utilized to determine the detector's spatial efficiency. A dime sized source with the established emission spectra was placed into the center of a rectangle of soil. This rectangle, including the source, was used as a lattice element to fill the region of space below the detector. The simulation was designed to track the energy distribution of pulses created in the sodium iodide crystal using the F8 tally, and was setup to isolate each source; thereby correlating detector response to source position. The simulation output required post-processing to determine conversion factors from counts per second to disintegrations per second. Post-processing accounted for subtraction of the Compton continuum, and average the data over the scanning pattern to obtain the expected spatial sensitivity during a characterization study. This was performed for the following photo-peaks: 609 keV (Bi-214), and 1764 keV (Bi-214). For calculation of the scan minimum detectable concentration, the surveyor efficiency coefficient from NUREG 1507 was supplanted in favor of a scan speed deviation factor. This was used because the detector utilizes computerized data collection (spatial and spectral). This report finds that, for two shielded 10.16 cm x 10.16 cm x 40.64 cm sodium-iodide crystals with integrated multi-channel analyzers, the minimum detectable concentration in surface soils is less than 1 pCi per gram Ra-226 for a 1 second survey measurement. These results assume a volumetric source with a maximum depth of 15.24 cm and a minimum decay time of 21 days. Verification of the system's capabilities was performed by sending soil samples from scanned areas, and locations where in-situ measurements were performed, to an independent laboratory for analysis. The laboratory results demonstrated that scanned area was principally comprised of soil containing less than 1 pCi per gram Ra-226. This borders the system MDC and it underestimated the concentration of radium in the soil. The probable causes of this is escape of radon gas from the surface soil. Radon is the daughter of radium, and has a high mobility in soil. If the gas escapes, then the progeny used as the detection proxy will be present in lower than expected concentrations. Radionuclide identification using high volume sodium-iodide crystals in low level characterization scans is demonstrated to be possible. Further system refinement will focus on developing a methodology to estimate a radon escape factor for site specific use. Accounting for radon escape in the top 15.24 cm of soil will allow the system to better estimate Ra-226 concentrations in soil. This is a significant advancement over the gross counting statistics used in most studies to satisfy MARSSIM survey requirements, because it will increase stakeholder confidence. (authors)

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Depleted Uranium Discrimination Using Spectral Ratios from Data-Starved Spectra - 18619

The Institute for Clean Energy Technology (ICET) has developed mobile surveying platforms for the retrieval of fired depleted uranium (DU) munitions. ICET surveying platforms are fitted with differential global positioning system (GPS), scintillation detectors, and central processing units (CPUs). The surveying technology has historically been used to assist facilities where DU contamination is a concern to locate, retrieve, and remediate DU-contaminated areas. Residence times over DU sources for mobile systems normally do not produce enough data to use gamma ray spectroscopy to verify the source type. Discussed is a potential method used to discriminate DU signatures in data-starved gamma ray spectral data collected during field surveys. Laboratory tests have shown that data-starved gamma ray spectra for zero-valence, oxide, and uranium ores can be distinguished from each other and from background by spectral ratioing. Zero-valence DU and DU oxide gamma ray signatures differ due to the attenuation of low-energy gammas emitted from U-238 daughters. DU signatures can be differentiated from naturally occurring uranium spectra due to the presence of daughters below U-234, primarily bismuth (Bi)-214, in the uranium decay series. Three primary regions of interest (ROI) within the analyzed test spectra are used to roughly characterize the shape of each test spectrum and compare them to background. The three ROIs are focused around the gamma-emitting daughters of U-238: thorium (Th)-234, protactinium (Pa)-234 metastable (m), and Bi-214. One of the three regions is considered the base region. This region is used to estimate what the counts in the other two regions should be by multiplying the counts in the ROIs by a ratio of background counts from an area previously found to be impacted. Using this spectral ratioing technique, a non-zero difference in spectral ratio values indicates a shift in the test spectra away from background. Calculating ratios between the base region and the other two regions allows for a graphical representation of the data in a two-dimensional spectral ratioing space, which is used to differentiate between the types of uranium sources previously mentioned. Surveying processes that are based on gross counts from scintillation counters can result in a large number of false positives as a result of shifting background signals or the presence of naturally occurring uranium. Application of the spectral ratioing technique can further assist in site characterization by analyzing all of the data-starved survey spectra to identify false positives or the need for additional data collection. Accurate surveys of DU testing and training ranges reduces the costs associated with range clean-up by discriminating clean areas from those requiring remediation. (authors)

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NORM Concentration Determination in Common Materials in an Urban Environment

The United States government performs searches for illicit radiation sources before and during large special events, such as State of the Union addresses, presidential inaugurations, or the recent papal visit. Clear detection of sources is difficult due to natural background radiation, which can vary greatly throughout a given search area. Background radiation is mostly a function of the materials used in roadways, sidewalks, and building exteriors. A team of scientists from Oak Ridge National Laboratory (ORNL), Lawrence Livermore National Laboratory (LLNL), the Remote Sensing Laboratory (RSL), and Lawrence Berkeley National Laboratory (LBNL) is exploring the nature and variability of background count rates in order to improve the performance of searches in urban areas. A series of background measurements have been and will continue to be taken at a Military Operations on Urban Terrain (MOUT) environment at the Fort Indiantown Gap (FTIG) National Guard training facility in Pennsylvania. This site replicates a small town with asphalt roads, concrete intersections, buildings, sidewalks, curbs, and gravel parking areas. Unlike an actual urban area, traffic and pedestrian access can be easily controlled to avoid interference with measurements. This paper documents the efforts focused on characterizing the various concentrations of radioactive material found in these materials at the site. The NORM concentrations determined from this work will be incorporated in to a large-scale simulation (a 'virtual test-bed') that can be used to investigate various search techniques and algorithms, detector suite configurations, and to produce representative synthetic data for future work. A combination of measurement and simulation was used to determine the concentration of {sup 40}K and the radioactive nuclides in the uranium series and the thorium series in several materials at the FTIG MOUT site. The predicted concentrations are consistent with other published results, and they matched favorably with synthetic data generated with MCNP6 models using the determined NORM concentrations and estimates of the FTIG environment as described by available construction plans and using standard material assumptions. Future measurements will incorporate lessons learned from this study. More measurements will be made of the concrete intersections at the site. The methodology explained in this report will also be carried out on building materials in an effort to characterize NORM concentrations in these background sources. Other modeling and simulation work that should be conducted includes a robust sensitivity analysis in which the effects of small changes to the model (and measurement) system can be characterized to help bound the uncertainty on the final NORM concentration predictions. (authors)

54 ENVIRONMENTAL SCIENCES↗

Fuels and Materials Challenges for the Very High Temperature Reactor

High Temperature Gas-cooled Reactors (HTGRs) featuring particle fuel are a very mature technology. Commercial deployment occurred in the mid-1980's with the Fort St.Vrain and Thorium Hochtemperatur Reaktor by providing electricity to the grids in the United States and West Germany, respectively. The technology was then adopted by Japan and China with the operation of the High Temperature Test Reactor in Oarai, Japan and the High Temperature Reactor (HTR-10) in China. These commercial reactors typically operate with an outlet coolant temperature of 750 deg. C to 800 deg. C. Increasing the outlet temperature of the HTGR to even higher temperatures above 900 deg. C will improve the thermodynamic efficiency of the system and enable application of a new class of gas reactor, the very high temperature reactor (VHTR), to provide process heat, electricity, and hydrogen to a broad range of industrial customers with the attendant benefits of improved energy security and reduced CO{sub 2} emissions. However, the increase in coolant outlet temperature presents a number of technical challenges associated with fuels and materials. For over a decade, the U.S. Department of Energy has been sponsoring a broad program of research and development with a goal of addressing the technical fuels and materials challenges to support deployment of a VHTR that could safely and economically operate at outlet temperatures of 750 to 950 deg. C. In summary, fuels and materials challenges exist with deploying a VHTR with an outlet temperature of 950 deg. C in the areas of structural materials, graphite and TRISO fuel. However, R and D is underway or has recently been completed suggesting that technical solutions are possible. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Pilot Test Remediation of a Fractured Bedrock Aquifer at the Maywood Superfund Site, Maywood, New Jersey - 19217

The U.S. Army Corps of Engineers (USACE) and Cabrera Services are conducting a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Pilot Test treatment of a fractured bedrock aquifer at the Formerly Utilized Sites Remedial Action Program (FUSRAP) Maywood Superfund Site (FMSS) located in Maywood, New Jersey (NJ), USA. The Maywood Chemical Company Superfund Site in Bergen County, NJ is listed on the United States Environmental Protection Agency (USEPA) Superfund National Priorities List (NPL). The National Superfund Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) identification number is NJD980529762. The Maywood Chemical Company Superfund Site (hereafter referred to as the FMSS) consists of 92 designated properties in the communities of Maywood, Lodi and Rochelle Park, NJ. These are collectively known as FMSS 'Vicinity Properties' and include property owned by the federal government (the Maywood Interim Storage Site, or MISS); the Stepan Company (former location of the Maywood Chemical Works, or MCW); 62 residential properties; three properties owned by the state or federal government; four municipal properties; and 21 commercial properties. The Stepan Company property includes contaminated buildings and three remediated U.S. Nuclear Regulatory Commission (NRC) licensed burial pits; the MISS also includes a contaminated building. Contamination on the FMSS is being addressed under three separate actions coordinated by the lead regulator USEPA Region 2. The USACE is addressing thorium (Th) and other wastes at the site defined as 'FUSRAP waste' in the Soils and Buildings and Groundwater Records of Decision (ROD) for the FMSS. Stepan Company is addressing other chemical wastes (non-FUSRAP waste) at the FMSS. The Groundwater ROD [1] was signed into agreement by USACE Division Commander in June 2012 and USEPA Region 2 Administrator in July 2012 and presents the selected remedial actions for Operable Unit (OU) 2 groundwater at the MISS and adjacent properties. The selected remedial action is removal of non-radiologically contaminated soils on the MISS containing arsenic, lithium, and benzene with concentrations above cleanup levels, and monitored natural attenuation (MNA) of arsenic, lithium, and benzene in groundwater. In situ treatment of arsenic in the overburden aquifer using oxidation reduction (redox) alteration will also be performed if needed to meet the groundwater cleanup levels after the source soil is removed. The need for in situ treatment will be determined during the Groundwater ROD review at least three to four years after the contaminated source soil removal is completed. The third action addressing non-FUSRAP chemical wastes will be the responsibility of the Stepan Company as a primary responsible party in this action. (authors)

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Assessment of Rare Earth Element Fingerprints for Distinguishing Between Site-Related Wastes and Background - 19441

Actinides such as uranium, thorium and radium are known to be present in sites associated with various phases of the cold war weapons research, development and production. Remediation of these sites as well as others associated with chemical plants that may have generated radioactive actinide-containing wastes have been the focus of the Formerly Utilized Sites Remedial Action Program (FUSRAP) for the past 20 years. The goal is to remediate a site to established cleanup standards as efficiently and cost-effectively as possible. For radiologically-contaminated sites, one potential challenge is the presence of non-FUSRAP media such as naturally-occurring radioactive material (NORM) or technologically-enhanced naturally-occurring radioactive material (TENORM), from non-FUSRAP sources, at concentrations exceeding site cleanup standards. Such NORM and TENORM, and even byproduct radionuclides from other unrelated activities on or near the site, can be mistaken for project waste and thus incur significant additional excavation and waste transport and disposal costs. Past studies have provided examples of NORM and non-FUSRAP waste and described strategies to distinguish them from FUSRAP waste. This paper describes various sources of NORM, summarizes the types of project-related waste at some active FUSRAP sites, and identifies TENORM sites from which radionuclides could possibly migrate via various environmental pathways to nearby FUSRAP sites. The authors also examine two Case Studies that calculate distinctive elemental ratios and are examples of tools which may be used for distinguishing FUSRAP waste from other radionuclides present in natural or other man-made contributors to background. Case Study I examines two bodies of data and calculates distinctive elemental ratios between pairs of rare earth elements (REE) to see if significant differences may exist between such ratios in unregulated coal ash residue, common in fill in well-established towns and cities, and FUSRAP waste. The first group of data, consisting of eighteen sample results, was obtained from the FUSRAP Maywood Superfund Site's historical data while the second was obtained from a paper which provided extensive data (more than 100 samples) on the REE content in fly ash residues from three major coal-producing areas in the United States. This example illustrates statistically significant differences in five of six REE ratios and thus provides a potential tool for distinguishing FUSRAP waste from coal ash-based NORM. Case Study II examines differences in the mean REE:Actinide and REE:REE ratios in Welsbach-impacted sample results to distinguish project waste from background. While the purpose of this study was to distinguish project waste from background levels of the radionuclides of concern (ROC), it provides a good example of how one or more ratios could potentially be used to distinguish FUSRAP waste from NORM. Lastly, the authors recommend that future projects ensure robust characterization, that considers all potential radionuclide contributors from both FUSRAP activities as well as from other contributors to background for the region during the Planning Phase of the Data Life Cycle described within the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). It is expected that the incremental characterization sampling and analysis costs will be dwarfed by potential savings from efforts to better delineate and limit remediation to FUSRAP wastes rather than other potentially unregulated contributors to regional background. Other agencies or commercial entities with radiological environmental liabilities similar to FUSRAP would benefit from similar considerations of REEs and other radionuclides that could contribute to regional background. (authors)

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Colonie, New York, FUSRAP Site: Pathway from Remediation to Redevelopment - 19465

The Colonie, New York, Formerly Utilized Sites Remedial Action Program (FUSRAP) Site consists of a 4.5-hectare (11.2-acre) US Department of Energy (DOE)-owned vacant property (Main Site) and 56 commercial and residential vicinity properties (VPs). The site was owned and operated by National Lead Industries (NL) from 1937 to 1984. The Main Site was used for manufacturing fuel and weapons components using uranium and thorium. Depleted uranium dust was emitted from exhaust stacks that contaminated the site and the VPs. NL also filled in portions of the site with industrial waste and released contaminants to groundwater. The state court shut the plant down in 1984. The site was acquired by DOE in 1985, which remediated the VPs and began to remediate the Main Site up to 1997. The US Army Corps of Engineers (USACE) undertook remedial actions beginning in 1997. The site has three Operable Units (Main Site, Groundwater, and VPs). The Main Site soil was remediated to residential standards except for three small easement areas. The soils in the easement areas are safe for exposure to workers. There is a groundwater plume beneath the site that will require the use of monitoring and temporary land use controls until cleanup standards are met. The VPs require no further action. A 2-year transition period from USACE to the DOE Office of Legacy Management (LM) began on June 18, 2018, with the receipt of the Site Closeout Report from USACE. LM has determined that the 4.5-hectare site is excess to its mission needs and intends to pursue sale of the property for redevelopment. There are several processes required before the disposal can occur. Organizations with similar sites that are federally owned and ready for private redevelopment may benefit from reviewing the Colonie site disposition processes. This paper will discuss (1) Determining disposal alternatives for the Colonie, New York, site. (2) Describing the federal requirements for the disposal of excess real property. (3) Communicating to stakeholders that the site is ready for disposal. (authors)

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Radon Considerations at Environmental Remediation Sites - 19469

Radon and how it is regulated poses many challenges to the U.S. Army Corps of Engineers (USACE) in executing the Formerly Utilized Sites Remedial Action Program (FUSRAP). These challenges include:, terminology; radon measurement methods and limitations; state certification and testing requirements; limited and potentially conflicting federal guidance; background considerations; and limited experience regarding application of guidance; among others. These challenges and others are discussed in detail. The FUSRAP Maywood Superfund Site (FMSS) is presented as a case study demonstrating these challenges and considerations to mitigate or address the challenges. The USACE, U.S. Environmental Protection Agency (USEPA), and the New Jersey Department of Environmental Protection (NJDEP) (NJDEP) have spent several years working on and continue to work through the radon issues at FMSS. The FMSS experience, information, and solutions presented in this paper will be helpful to other environmental sites with radium and thorium contamination. (authors)

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Disposal of a pretreated oil sludge by the cementation method

Radioactive oil sludge is generated in oil production rigs worldwide and in large quantities. However, in Brazil, there is no disposal route or well-defined treatment option for this waste. This sludge is classified as TENORM due to the presence of Potassium-40 and the radionuclides of the natural decay chains of thorium and uranium. The management of this radioactive waste has been in situ packaging on the offshore platforms, followed by its transport to storage facilities onshore. Long term storage is problematic due to the high content of hydrocarbons, sulfur and water, which generates the toxic gas H{sub 2}S and the corrosive sulfuric acid. Ozonation, an advanced oxidation process (AOP) can be considered an attractive option of treatment, and followed by cementation can improve safety in long-term storage. This work aims at investigating if the ozone process was able to enhance the immobilization capacity of oil sludge. Oil sludge from different drums and mixed oil sludge (obtained by mixing equal parts of each drum) were analyzed by ICP. Solidification of oil sludge with Portland cement enhances safety of the waste disposal. In addition, ozonation treatment is efficient in the degradation of organic compounds, increasing the resistance of the solidified material.

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Pilot Test Remediation of a Fractured Bedrock Aquifer at the Maywood Superfund Site, Maywood, New Jersey - 20073

The U.S. Army Corps of Engineers (USACE) and Cabrera Services are conducting a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Pilot Test treatment of a fractured bedrock aquifer at the Formerly Utilized Sites Remedial Action Program (FUSRAP) Maywood Superfund Site (FMSS) located in Maywood, New Jersey (NJ), USA. The Maywood Chemical Company Superfund Site in Bergen County, NJ is listed on the United States Environmental Protection Agency (USEPA) Superfund National Priorities List (NPL). The National Superfund Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) identification number is NJD980529762. The Maywood Chemical Company Superfund Site (hereafter referred to as the FMSS) consists of 92 designated properties in the communities of Maywood, Lodi and Rochelle Park, NJ. These are collectively known as FMSS 'Vicinity Properties' and include property owned by the federal government (the Maywood Interim Storage Site, or MISS); the Stepan Company (former location of the Maywood Chemical Works, or MCW); 62 residential properties; three properties owned by the state or federal government; four municipal properties; and 21 commercial properties. The Stepan Company property includes contaminated buildings and three remediated U.S. Nuclear Regulatory Commission (NRC) licensed burial pits; the MISS also includes a contaminated building. Contamination on the FMSS is being addressed under three separate actions coordinated by the lead regulator USEPA Region 2. The USACE is addressing thorium (Th) and other wastes at the site defined as 'FUSRAP waste' in the Soils and Buildings and Groundwater Records of Decision (ROD) for the FMSS. Stepan Company is addressing other chemical wastes (non-FUSRAP waste) at the FMSS. The Groundwater ROD [1] was signed into agreement by USACE Division Commander in June 2012 and USEPA Region 2 Administrator in July 2012 and presents the selected remedial actions for Operable Unit (OU) 2 groundwater at the MISS and adjacent properties. The selected remedial action is removal of non-radiologically contaminated soils on the MISS containing arsenic, lithium, and benzene with concentrations above cleanup levels, and monitored natural attenuation (MNA) of arsenic, lithium, and benzene in groundwater. In situ treatment of arsenic in the overburden aquifer using oxidation reduction (redox) alteration will also be performed if needed to meet the groundwater cleanup levels after the source soil is removed. The need for in situ treatment will be determined during the Groundwater ROD review at least three to four years after the contaminated source soil removal is completed. The third action addressing non-FUSRAP chemical wastes will be the responsibility of the Stepan Company as a primary responsible party in this action. (authors)

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