TPM-B - Environmental Monitoring North 222ABC 14:30 - 17:45
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BREAK
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TPM-B.
Gamma Irradiation of Plantain (MUSCA PARADISIACA) From Mechanized Farmlands at Varying Optimum Dose Range BB Oladele*, Federal University of Technology Akure
; AM Arogunjo, Federal University Of Technology Akure.
Abstract: The shelf life extension and the effect irradiation on sprouting of Plantain (MUSCA PARADISIACA) using different doses of gamma radiation was studied. Dose range of 100Gy to 140Gy was used in delaying the sprouting of the irradiated plantains. Macro and micro elements in the samples was considered in this study. The proximate composition,ash determination, crude fat, protien and fibre content were all determined using standard laboratory techniques. The results of the ripe and unripped pantains at varying optimum dose range were recorded. The control sample and plantain exposed to 150Gy have no difference in physical appearance through out the first 6 days of exposure. There was shrinking on the peel of the 300Gy and 450Gy after the fourth day till spoilage.From the result, exposure of plantain to gamma radiation delayed the ripening of the fruit and extend its spoilage time effectively.Gamma radiation has very little effect on the organoletic constitute of the plantain.
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TPM-B.1
14:30 US EPA Superfund Counts Per Minute (CPM) Model St Walker*, U.S. Environmental Protection Agency
Abstract: The U.S. Environmental Protection Agency (EPA) Superfund program is finishing up a new Counts Per Minute (CPM) calculator to correlate real-time survey results, which are often expressed as counts per minute, to contaminant concentrations that are more typically provided as in risk assessments or for cleanup levels, which are usually expressed in pCi/g or pCi/m2. Currently there is no EPA guidance for Superfund sites on correlating count per minute field survey readings back to risk, dose, or other Applicable or Relevant and Appropriate Requirements (ARAR) based concentrations. The CPM calculator is a web-based model that estimates a gamma detector response for a given level of contamination. The intent of the CPM calculator is to facilitate more real-time measurements within a Superfund response framework. This calculator provides a rapid, exceptionally cost-effective assessment of contamination and cleanup standards based on field instrument data, which minimizes the use of more expensive sample collection and laboratory analysis. Detector data is based on four sizes of gamma scintillation detectors by Ludlum Measurements Inc. When using the CPM calculator to address volumetric sources, there are six different options for source material, which are soil, concrete, plate glass, wood, steel, and drywall. Underpinning the CPM calculator is an analysis on the density of the six different materials and the photonic energy of radionuclides on exposure rate results. A correction factor for cpm analysis established between these calculator results and lab sampling analysis may be needed to account for ground truthing and other field nuances. The user should verify calculator results with lab sampling. This presentation would go over the CPM calculator portions that have finished peer review and may be issued by HPS 2021
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TPM-B.2
14:45 Radiation Drones: Flying into the Future AS Orechwa*, Tetra Tech
Abstract: The recent advances in radiation detection and unmanned aerial vehicles (UAVs) technologies in conjunction with an increased interest from the government, academic, and private sectors in a post-Fukushima world, there has been rapid growth in the development and innovation of UAVs for the purposes of radiation mapping. The volume of scientific publications regarding UAVs used for radiation mapping or scanning has increased significantly over the past decade. A comprehensive literature search discovered well over 100+ peer reviewed international journal publications, most within last two years, related to the theory, design, development, and/or validation of UAV radiation mapping systems throughout the world. This presentation briefly summarizes the literature and pertinent findings and gives a status update on recent advances of the UAV radiation mapping sector. The author then provides a brief overview of his own research (past and current) being performed using high-precision autonomous terrain-following UAVs for the purposes of conducting sophisticated radiological surveys at abandoned legacy uranium mines within the Colorado Plateau, and he presents the general results and findings of this research.
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TPM-B.3
15:00 Design of a Database for a Multi-station Weather and Radiation Monitoring System CC Huang*, University of Michigan
; AJ Kent, University of Michigan; S Tawfik, University of Michigan; JD Noey, University of Michigan; KJ Kearfott, University of Michigan
Abstract: The growing complexity of data collection systems poses new challenges for maintaining the software infrastructure needed for processing and analysis. Modern database management systems provide a scalable and efficient means of data storage and retrieval to meet these needs and are highly applicable in radiation and weather data systems. In order to integrate a database into the existing infrastructure, an entirely new data pipeline was implemented to handle input streams and preprocessing. Each incoming data stream was analyzed and categorized by format and type in order to design the relational table structure of the database. Using these design decisions, a MySQL database server was built and populated with test data. Preprocessing software was written to guard the database and server credentials as well as perform unit conversions, time-stamp alignments, and input sanitization before pushing the data into storage. This software was initially designed for portability via installation on multiple machines for direct access to data streams but was redesigned to run on a centralized virtual Linux server. Operating the virtual machine allowed for proper isolation of database access and a centralized interface between the data streams and the software. This new pipeline will improve the efficiency of the data flow and allow for the collected radiation and weather measurements to be more accessible and consistent, enabling future advancements in analysis and prediction.
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15:15 BREAK
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TPM-B.4
15:45 Calibration of Charcoal Canister Radon Measurement Devices in an Environmental Chamber and a Natural Indoor Environment TW Kennings*, University of Michigan
; LA Mata, University of Michigan; NP Piersma, University of Michigan; JD Noey, University of Michigan; KJ Kearfott, University of Michigan
Abstract: Charcoal canisters are commonly used for radon screening. Canisters made from the same charcoal batch, which may vary in adsorptive abilities, are typically calibrated in commercial large volume environmental chambers with constant and controlled temperature, relative humidity, pressure, and radon concentration. Ideally, the operation of these chambers should be traceable to international standards. Canister calibration and quality control, and thus radon screening, could be more accessible if large and expensive chambers were not necessary for the periodic validation of calibrations. This study compares calibrations obtained from a commercial radon chamber and from a less controlled basement storage room with consistently elevated radon. It also examines the effects of several spectral analysis methods on calibration accuracy and precision. A group of canisters was sent to a commercial radon environmental chamber with controlled and constant radon concentration. Another group of canisters manufactured from the same charcoal batch was placed in a basement boasting an elevated naturally occurring radon concentration, ~1,500 Bq m-3 for this experiment. Radon exposure durations ranged from 0.5 to 7 d. Counts from three regions of interest encompassing the Bi-214 peak, three Pb-214 peaks, and all four peaks together, respectively, were analyzed from spectra obtained using a 7.6 cm diameter x 7.6 cm thick NaI(Tl) system. A previously developed radon equilibration model was applied to retrieve a calibration coefficient for the set of canisters. Background subtraction and curve stripping were applied and an examination of these techniques’ impact on the calibration was performed. Initial results suggest that controlled environmental chambers may not be necessary to obtain an accurate calibration of the charcoal canisters provided that the change in radon as a function of time in the calibration space is measured and relatively constant.
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TPM-B.5
16:00 Assessing Radon Exposure in the Vicinity of a Residential Radon Mitigation System Exhaust LS Lebel*, Canadian Nuclear Laboratories
; A John, Canadian Nuclear Laboratories; K Vu, Canadian Nuclear Laboratories; V Korolevych, Canadian Nuclear Laboratories
Abstract: Sub-slab depressurizations systems are a proven method for radon mitigation in residential buildings. It is common to install the discharges of these radon mitigation systems near ground level in northern climates because vertically oriented, above-roof-line discharges often have issues with ice and snow obstruction during the winter months. Discharging the radon-laden gas near ground level, however, also elevates the ground level outdoor radon concentrations, and raises the possibility of radon re-entrainment into nearby homes. The present study assesses the expected outdoor radon concentrations in the vicinity of two neighboring buildings with a series of computational fluid dynamics calculations. The study also explores how different meteorological, venting, and building geometry parameters influence the resulting radon concentrations. Results show that outdoor concentrations can be up to 10% of the original concentration close to the vent. These concentrations become smaller at greater distances. The direction of the prevailing wind was a particularly important parameter because it influenced the formation of circulating building cavities and building wakes where radon could accumulate. The wind speed and atmospheric stability generally had smaller, but still important influences on the outdoor radon concentrations. The computational results were subsequently coupled to the local frequencies of prevailing wind and weather conditions in order to estimate the elevated indoor radon exposure that could occur due to radon re-entrainment into homes. The aim of the study was to develop a method that can be used to inform guidance on setback distances between the radon discharges and potential re-entrainment points, such as open windows or fresh air intakes in both the emitting home and neighbouring homes.
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TPM-B.6
16:15 Distribution of Natural Radionuclides in Surface Soils around Nevada National Security Site X Liu*, MSTS
; RW Warren, MSTS
Abstract: According to the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) publications, contributions of terrestrial gamma doses are mainly from the presence of 40K and of 238U and 232Th together with their progeny in various rocks and soils. A survey of soil distributions of radionuclides 40K, 238U, and 232Th was performed in Nevada National Security Site (NNSS) using in situ gamma spectroscopy analysis. The average activity concentrations of 40K, 238U, and 232Th were 867 ± 38 Bq kg-1 (range from 150 to 1297 Bq kg-1), 50 ± 6 (range from 29 to 74 Bq kg-1), and 56 ± 8 Bq kg-1 (range from 11 to 96 Bq kg-1) respectively. The terrestrial gamma dose rates around NNSS was estimated from 26 to 144 nSv h-1 with mean value of 93 ± 9 nSv h-1. The results are compared with available published data and with results from soil samples from the NNSS. The radiological effects of the main naturally occurring radionuclides in NNSS are discussed.
This work was done by Mission Support and Test Services, LLC, under Contract No. DE-NA0003624 with the U.S. Department of Energy. DOE/NV/03624--0992.
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TPM-B.7
16:30 Using Spanish Moss as a Bio-indicator for Air Pollution in the Low Country of Savannah River Basin Z Sun, Unversity of Nevada, Las Vegas
; C Hall*, Unversity of Nevada, Las Vegas; W Frey, University of California, Davis
Abstract: Spanish moss (Tillandsia usneoides) is epiphyte that grows upon larger trees in tropical and subtropical climates. It is a common plant in the low country of the savannah river basin. It absorbs nutrients and water through its leaves from the air and rainfall, which makes it ideal for serving as a bio-indicator of local air pollution. In this study, we collected samples of Spanish moss along the savannah river, near all the industrial sites and superfund sites from Aiken, SC to Savannah, GA, in order to seek the relationship of heavy metals in the Spanish moss and the air pollution in the low country of Savannah River Basin. All the samples were dried and grinded into fine powder, and then studied systematically by instrumental neutron activation analysis (INAA). After irradiation of the samples with thermal and epithermal neutrons in the PULSTAR Reactor, all of short-lived, medium-lived, and long-lived isotopes spectra were collected with HPGe spectrometers. The preliminary results indicate that: (1) INAA can determine the level of elements in Spanish moss with high accuracy and extreme sensitivity. It is an appropriate tool for conducting multi-element analysis in biological samples; (2) The concentrations of heavy metals in the samples has clearly correlations with the pollution sources in the Savannah River Area, which proves that Spanish moss can serve as an efficient bio-indicator of air pollution.
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TPM-B.8
16:45 Radiological Assessment of Groundwater from Selected Water Treatment Plants in Saudi Arabia GA Asuni*, Saudi Aramco
; SM Qahtani, Saudi Aramco
Abstract: An assessment of groundwater samples collected from several water treatment plants (WTPs) was performed to determine the presence of natural radioactivity. Samples before and after the treatment process were collected with a specific interest in the process of backwash and reject water to ascertain the potential for environmental impact. Previous studies have shown that groundwater contains some level of natural radioactivity that is reduced to acceptable limits before use. The elevated level of radioactivity is due to the presence of natural radioactive material from the Uranium and Thorium series present in the aquifer and the dissolution of the associated daughter products in the water. The water treatment process enhances the level of radioactivity in both the filtration media and process reject effluent. The liquid wastes are generated when the filter media are backwashed or rejected water through reverse osmosis (RO) operation. The waste may contain high amounts of natural radioactivity and should be disposed of in a manner that does not negatively impact the environment or potentially exposes workers and/or the public. This study involves the radiological analysis of 240 water samples collected at 15 selected WTPs. All the samples were analyzed for gross alpha and beta activity, Radium 226 and 228 using standard protocols with a liquid scintillation counter. The gross alpha beta activity ranged from 0.14 Bq/L – 13.80 Bq/L for backwashed water and from 0.57 Bq/L – 14.61 Bq/L for RO rejected water. The total radium concentration from Ra-226 and Ra-228 were found to range from 0.08 Bq/L – 4.25 Bq/L and 0.08 Bq/L – 5.39 Bq/L for backwashed water and RO rejected water respectively. The results were compared to the US Nuclear Regulatory Commission direct discharge criteria for contaminated wastewater and appropriate disposal methods were recommended.
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TPM-B.9
17:00 Assessment of radiological content of imported bottled drinking water purchased in Saudi Arabia oa Al-Somali*, Saudi Aramco
Abstract: The objective of the study was to assess the radiological content of bottled drinking water of 25 international brands imported to Saudi Arabia.
The assessment was based on the screening methodology detailed in World Health Organization (WHO) report, 4th edition 2017. The methodology described by the WHO report for assessing radiological hazards in drinking water has two stages: (1) Initial screening for a gross alpha and/or beta activity concentration to determine whether the activity concentrations are below levels at which no further action is required; and (2) if these screening levels are exceeded, investigation of the concentrations of individual radionuclides is conducted. Then the concentrations of individual radionuclides will be determined and compared with the guidance values. The WHO guideline for assessing the safety of drinking water are 0.5 Bq/l for gross alpha activity concentration and 1.0 Bq/l for gross beta activity concentration to ensure an exposure lower than Individual Dose Criterion (IDC) of 0.1 mSv per year.
A standardized method — the evaporation technique — was used to determine concentrations of gross alpha and gross beta activities. Each sample was evaporated then the activity concentration of the remaining residue was measured by using the ZnS (Ag) scintillator detector system for gross alpha analysis. The determination of gross beta activity concentration was achieved through measuring the remaining residue by a proportional counting system. The method for determination of gross alpha and beta is specified by International Organization for Standardization (ISO) in standards ISO 9696 and ISO 9697, respectively. The laboratory procedure is accredited to ISO 17025.
The highest activity concentration across the samples for alpha activity concentration was 0.18 Bq/l and the beta activity concentration was 0.34 Bq/l. The Committed Effective Doses (CED) resulting from the consumption of these brands were estimated to be below the WHO recommended limit of 0.1 mSv per year.
The study concluded that the water samples have radioactivity concentrations below the World Health organization (WHO) recommended guidance level and are safe to drink. Further confidence in the study can be provided by collection of a greater number of samples over prolonged periods.
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TPM-B.10
17:15 Unique Techniques To Estimate Key Parameters For The Clarification Of The Age and Source of A Ground Water Leak At A Nuclear Power Plant FJ Mis, M.I.S., Inc.
; GC Jones*, M.I.S., Inc.; TH Darrah, Ohio State University; FJ Mis
Abstract: Ground Water Leaks from Nuclear Power Plants are cause for Significant Concern. Unmonitored release of radioactivity to the environment violates Federal and State Law. The release of radioactivity to private property is a costly legal risk and a public relations nightmare. Even if the actual risk to human health is low, it is not an acceptable risk to the neighboring population or politically to the utility. A significant number of key components are located beneath the surface at a nuclear site. Piping for many radioactive systems are below grade and leaks can go undetected until radioactivity is found in groundwater sample wells. Nuclear plants have underground piping monitoring programs to detect potential leaks. Underground piping inspections are a relatively new program at many sites and plant radioactivity may already exist in slow moving groundwater systems. M.I.S., Inc. in cooperation with Ohio State University has developed a process which incorporates 3 key processes for identification of the age, rate of movement and potential source of an underground leak to aquifer event. Included in this process is a proprietary Ohio State technique for noble gas age determination. When this is combined with radio-isotopic analysis for some key radioisotopes, significant information is available. This combined process is to become an ASTM standard or Patent, based on Ohio State preferred processes. We consider this a significant tool for the determination of systems, structures and components (SSC) material condition.
Presenting Author: Frederic J. Mis. 585-797-4578
FJMRP@yahoo.com
M.I.S., Inc
634 Lake RD
Webster, NY
14580
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TPM-B.11
17:30 Major ions and Uranium content in groundwater around some large-scale mineral mining and processing sites in Nigeria OO Ife-Adediran*, Federal University of Technology Akure
; AM Arogunjo, University of Medical Sciences Ondo; OS Ajayi, Federal University of Technology Akure; C Walther, Institute of Radioecology and Radiation Protection Hanover
Abstract: In the absence of monitoring, impact assessment and remediation, the detrimental effects of industrialization the environment may become unduly severe. Therefore, this study serves as an assessment of groundwater in the vicinity of some mineral mining and processing sites in Nigeria. The collected samples were analysed for anions and cations concentrations as well asuranium-238 activity concentrations using analytical techniques such as ion-chromatography and Inductively Coupled Plasma - Optical Emission Spectrometry. Fluoride, sulphate and phosphate were found in some locations at concentrations that are unsafe for human consumption. The occurrence of these parameters above permissible limits alludes to the impact of anthropogenic activities in the investigated environmental media. However, the activity concentration ofuranium-238 in the groundwater has a range of 0.00 to 47.50 ± 0.06 Bq/l and these values are below the recommended limit of 100 Bq/l as suggested by relevant local and international regulatory agencies. The results are expected to engender possible interventional actions in the areas of concern and provide useful data for the regulation of further industrial activities in the study locations
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