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Direct measurement of strontium-90 and uranium-238 in soils on a real-time basis: 1994 summary report

Description: Traditional methodologies for quantitative characterization of radionuclide-contaminated soils over extended areas are often tedious, costly, and non-representative. A rapid characterization methodology was designed that provides reliable output with spatial resolution on the order of a few meters or less. It incorporates an innovative sensor of square plastic scintillating fibers that has been designed to be placed directly on or above a contaminated soil to detect and quantify high-energy beta particles associated with the decay chains of uranium and/or strontium. Under the direction and auspices of the DOE`s Characterization, Monitoring, and Sensor Technology Integrated Program, Pacific Northwest Laboratory (PNL) constructed a high-energy beta scintillation sensor that was optimized for the detection and quantification of uranium and strontium contamination in surface soils (in the presence of potentially interfering natural and anthropogenic radionuclides), demonstrated and evaluated this detector in various field and laboratory scenarios, and provides this document in completion of the aforementioned requirements.
Date: April 1, 1995
Creator: Schilk, A.J.; Hubbard, C.W.; Knopf, M.A. & Thompson, R.C.
Partner: UNT Libraries Government Documents Department

Multi-agency radiation survey and site investigation manual (MARSIM). Final report

Description: The MARSSIM provides information on planning, conducting, evaluating, and documenting building surface and surface soil final status radiological surveys for demonstrating compliance with dose or risk-based regulations or standards. The MARSSIM is a multi-agency consensus document that was developed collaboratively by four Federal agencies having authority and control over radioactive materials: Department of Defense (DOD), Department of Energy (DOE), Environmental Protection Agency (EPA), and Nuclear Regulatory Commission (NRC). The MARSSIM`s objective is to describe a consistent approach for planning, performing, and assessing building surface and surface soil final status surveys to meet established dose or risk-based release criteria, while at the same time encouraging an effective use of resources.
Date: December 1, 1997
Partner: UNT Libraries Government Documents Department

What is a Beryllium Measurement? A Critical Look at Beryllium

Description: DOE workplaces strive to comply with the 10 CFR 850.31(b)(1) surface concentration release criterion. The usual planning considerations for demonstrating compliance are these: how many swipes, and where; which sample preparation and analytical methods; what reporting limits; and what sample statistic to compare with the criterion. We have reviewed swipe samples from hundreds of Nevada Test Site workplaces: office buildings; experimental facilities; forward area field units; shops; and tunnels. Our experiences have led us to a critical examination of the inner workings of the measurement process itself, involving details generally taken for granted when those usual questions are asked. In this presentation we dissect the ICP-AES Be measurement process. We discuss calibration options and how they impact the distributions of analytical results. We look at distributions of blank results obtained from different labs, and discuss their relevance to determining reporting limits. We examine the way measurements are made from spectra, how that process impacts our understanding of the actual statistical distributions of Be measurements, and how interferences can affect Be measurements. Our objective is to gain sufficient confidence in the measurement process so that the usual questions will make sense and the survey results will be credible. Based on our observations, we offer these recommendations: prepare calibration samples in digested blank swipes; force the calibration line through (0,0); base reporting limits on field blank measurement distributions rather than 40 CFR 236 calculations; use, but do not believe, the usual lognormal distribution assumption; and avoid the 234.861 nm emission line.
Date: March 1, 2006
Creator: Davis, Charles; Field, Dan; Hess, John & Jensen, Dan
Partner: UNT Libraries Government Documents Department

Potential dose distributions at proposed surface radioactvity clearance levels resulting from occupational scenarios.

Description: The purpose of this report is to evaluate the potential dose distribution resulting from surface radioactivity, using occupational radiation exposure scenarios. The surface radioactivity clearance values considered in this analysis may ultimately replace those currently specified in the U.S. Department of Energy (DOE) requirements and guidance for radiological protection of workers, the public and the environment. The surface contamination values apply to radioactive contamination deposited on a surface (i.e., not incorporated into the interior of the material). For these calculations, the dose coefficients for intake of radionuclides were taken from ICRP Publication 68 (ICRP 1994), and external exposure dose coefficients were taken from the compact disc (CD) that accompanied Federal Guidance Report (FGR) 13 (Eckerman et al. 1999). The ICRP Publication 68 dose coefficients were based on ICRP Publication 60 (ICRP 1990) and were used specifically for worker dose calculations. The calculated dose in this analysis is the 'effective dose' (ED), rather than the 'effective dose equivalent' (EDE).
Date: August 2, 2011
Creator: Kamboj, S.; Yu, C. & Rabovsky, J.
Partner: UNT Libraries Government Documents Department

Hydrogen Contamination of Niobium Surfaces

Description: The presence of hydrogen is blamed for dramatic reductions in cavity Q's. Hydrogen concentration is difficult to measure, so there is a great deal of Fear, Uncertainty, and Doubt (FUD) associated with the problem. This paper presents measurements of hydrogen concentration depth profiles, commenting on the pitfalls of the methods used and exploring how material handling can change the amount of hydrogen in pieces of niobium. Hydrogen analysis was performed by a forward scattering experiment with Helium used as the primary beam. This technique is variously known as FRES (Forward Recoil Elastic Scattering), FRS, HFS (Hydrogen Forward Scattering), and HRA (Hydrogen Recoil Analysis). Some measurements were also made using SIMS (Secondary Ion Mass Spectrometry). Both HFS and SIMS are capable of measuring a depth profile of Hydrogen. The primary difficulty in interpreting the results from these techniques is the presence of a surface peak which is due (at least in part) to contamination with either water or hydrocarbons. With HFS, the depth resolution is about 30 nm, and the maximum depth profiled is about 300 nm. (This 10-1 ratio is unusually low for ion beam techniques, and is a consequence of the compromises that must be made in the geometry of the experiment, surface roughness, and energy straggling in the absorber foil that must be used to filter out the forward scattered helium.) All the observed HFS spectra include a surface peak which includes both surface contamination and any real hydrogen uptake by the niobium surface. Some contamination occurs during the analysis. The vacuum in the analysis chamber is typically a few times 10{sup -6} torr, and some of the contamination is in the form of hydrocarbons from the pumping system. Hydrocarbons normally form a very thin (less than a monolayer) film which is in equilibrium between arrival rate and ...
Date: October 1993
Creator: Nguyen-Tuong, Viet & Doolittle, Lawrence
Partner: UNT Libraries Government Documents Department

Alpha characterization of concrete surfaces at Decontamination & Decommissioning (D&D) sites

Description: Waste minimization and worker protection at D&D sites requires continual and extensive characterization for radioactive contamination. Contamination detectors that are sensitive, rugged, fast, and capable of covering large areas are needed. The concrete surface monitor (CSM) developed at LANL supports both characterization and waste minimization efforts at D&D sites containing large concrete surfaces and structures of different forms and shapes. This report describes the CSM design and the results of several field experiments.
Date: February 1, 1995
Creator: Vu, T.Q.; Rawool-Sullivan, M.W.; Koster, J.; Stout, D. & Beasinger, A.
Partner: UNT Libraries Government Documents Department

Unrestricted release measurements with ambient air ionization monitors

Description: Radiation monitoring systems based on the long-range alpha detection (LRAD) technique, such as the BNFL Instruments IonSens{trademark}, provide a single contamination measurement for an entire object rather than the more familiar individual readings for smaller surface areas. The LRAD technique relies on the ionization of ambient air molecules by alpha particles, and the subsequent detection of these ions, rather than direct detection of the alpha particles themselves. A single monitor can detect all of the ions produced over a large object and report a total contamination level for the entire surface of that object. However, both the unrestricted release limits specified in USDOE Order 5400.5 (and similar documents in other countries), and the definitions of radioactive waste categories, are stated in terms of contamination per area. Thus, conversion is required between the total effective contamination as measured by the LRAD-based detector and the allowable release limits. In addition, since the release limits were not written assuming an averaging detector system, the method chosen to average the assumed contamination over the object can have a significant impact on the effective sensitivity of the detector.
Date: March 1, 1999
Creator: MacArthur, D.; Gunn, R.; Dockray, T. & Luff, C.
Partner: UNT Libraries Government Documents Department

Progress of electro-hydraulic scabbling technology for concrete decontamination

Description: Concrete decontamination from organics, metals, and radionuclides requires removal of up to one inch of the surface layer. The Electro- Hydraulic Scabbling (EHS) technique has been developed within a 3- phase program. A prototype 8 kW EHS unit was designed and assembled in Phase II. This system was tested initially by scabbling noncontaminated concrete, and later at the DOE Fernald site where a concrete floor containing uranium was decontaminated. In the latter test, the unit operated without problems and reduced the counts per minute by more than 90%. Currently in Phase III, a larger 30 kW unit has been assembled and prepared for testing/demonstration.
Date: May 1, 1997
Creator: Goldfarb, V. & Gannon, R.
Partner: UNT Libraries Government Documents Department

Methods for the measuring surface tritium inside TFTR using beta decay

Description: Three potential methods for evaluating the surface tritium content of the TFTR vacuum vessel are described, each based on a different technique for measuring the in situ beta emission from tritium. These methods should be able to provide both a local and a global assessment of the tritium content within the top {approximately}1{mu}m of the inner wall surface.
Date: March 1, 1995
Creator: Zweben, S.J.; Johnson, D.W.; Hill, K.W.; Ku, L.P.; Lemunyan, G.; Loesser, D. et al.
Partner: UNT Libraries Government Documents Department

Sampling and analysis plan for the gunite and associated tanks interim remedial action, wall coring and scraping at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: This Sampling and Analysis Plan documents the procedures for collecting and analyzing wall core and wall scraping samples from the Gunite and Associated Tanks. These activities are being conducted to support the Comprehensive Environmental Response, Compensation, and Liability Act at the gunite and associated tanks interim remedial action at Oak Ridge National Laboratory in Oak Ridge, Tennessee. The sampling and analysis activities will be performed in concert with sludge retrieval and sluicing of the tanks. Wall scraping and/or wall core samples will be collected from each quadrant in each tank by using a scraping sampler and/or a coring drill deployed by the Houdini robot vehicle. Each sample will be labeled, transported to the Radioactive Materials Analytical Laboratory, and analyzed for physical and radiological characteristics, including total activity, gross alpha, gross beta, radioactive strontium and cesium, and other alpha- and gamma-emitting radionuclides. The data quality objectives process, based on US Environmental Protection Agency guidance, was applied to identify the objectives of this sampling and analysis. The results of the analysis will be used to (1) validate predictions of a strontium concrete diffusion model, (2) estimate the amount of radioactivity remaining in the tank shells, (3) provide information to correlate with measurements taken by the Gunite Tank Isotope Mapping Probe and the Characterization End Effector, and (4) estimate the performance of the wall cleaning system. This revision eliminates wall-scraping samples from all tanks, except Tank W-3. The Tank W-3 experience indicated that the wall scrapper does not collect sufficient material for analysis.
Date: February 1, 1998
Partner: UNT Libraries Government Documents Department

Acceptance Test Report for the high pressure water jet system canister cleaning fixture

Description: This Acceptance Test confirmed the test results and recommendations, documented in WHC-SD-SNF-DTR-001, Rev. 0 Development Test Report for the High Pressure Water Jet System Nozzles, for decontaminating empty fuel canisters in KE-Basin. Optimum water pressure, water flow rate, nozzle size and overall configuration were tested
Date: October 25, 1995
Creator: Burdin, J.R.
Partner: UNT Libraries Government Documents Department

Development of guidance on applications of regulatory requirements for low specific activity materials and surface contaminated objects

Description: In 1985, the International Atomic Energy Agency issued revised regulations for the safe transport of radioactive material. Significant among the changes were major revisions to requirements for Low Specific Activity (LSA) material and Surface Contaminated Objects (SCOs). In preparation for the adoption of these requirements into regulations in the United States, it became apparent that guidance on how to apply these requirements, clarifying technical uncertainties and ensuring proper implementation, would be needed both by the regulators and those regulated. Thus, the US Department of Transportation and the US Nuclear Regulatory Commission, with the assistance of staff from Oak Ridge National Laboratory, are preparing regulatory guidance for LSA material and SCO transport. The guidance will present examples of acceptable methods for demonstrating compliance with the revised rules. Ideas being investigated for inclusion in the pending guidance are discussed in this paper. Under current plans, the guidance will be issued for public comment prior to final issuance of the guidance in 1997.
Date: April 1, 1997
Creator: Pope, R.B.; Easton, E.P. & Shankman, S.F.
Partner: UNT Libraries Government Documents Department

E-PERM alpha surface monitor

Description: Innovative Technology Summary Reports are designed to provide potential users with the information they need to quickly determine if a technology would apply to a particular environmental management problem. They are also designed for readers who may recommend that a technology be considered by prospective users. Each report describes a technology, system, or process that has been developed and tested with funding from DOE's Office of Science and Technology (OST). The E-PERM{reg{underscore}sign} Alpha Surface Monitor is an integrating electret ion chamber innovative technology used to measure alpha radiation on surfaces of materials. The technology is best used on surfaces with low contamination levels such as areas with potential for free release, but can also be used in areas with higher levels of contamination. Measurement accuracy and production of the E-PERM {reg{underscore}sign} Alpha Surface Monitor compared favorably with the baseline technology. The innovative technology cost is approximately 28% higher than the baseline with an average unit cost per reading costing %6.04 vs. $4.36; however, the flexibility of the E-PERM{reg{underscore}sign} Alpha Surface Monitor may offer advantages in ALARA, reduction of operator error, waste minimization, and measurement accuracy.
Date: December 16, 1999
Creator: Fricke, V.
Partner: UNT Libraries Government Documents Department

Assessment of surface contamination with contact mechanics

Description: The authors are particularly interested in the work of adhesion measurements as a means to facilitate the understanding of the adhesive failure mechanisms for systems containing encapsulated and bonded components. Of the several issues under investigation, one is the effect of organic contamination on the adhesive strength for several types of polymer/metal interface combinations. The specific question that the authors are trying to address is at what level of contamination does adhesive strength decrease. The use of contact mechanics, the JKR method, is a good approach for studying this question. Another approach being studied is the use of interracial fracture mechanics. The model contaminant is hexadecane--non-polar, medium molecular weight hydrocarbon fluid. They choose hexadecane because it replicates typical machining fluids, is nonreactive with Al surfaces, and should not dissolve readily into the adhesive systems of interest. The application of a uniform, controllable and reproducible hexadecane layer on Al surfaces has proven to be difficult. A primary concern is whether studies of model systems can be extended to systems of technological interest. The JKR theory is a continuum mechanics model of contact between two solid spheres that was developed by Johnson, Kendall and Roberts. The JKR theory is an extension of Hertzian contact theory and attributes the additional increase in the contact area between a soft elastomeric hemisphere to adhesive forces between the two surfaces. The JKR theory allows a direct estimate of the surface free energy of interface as well as the work of adhesion (Wa) between solids. Early studies performed in this laboratory involved the determination of Wa between silicone (PDMS) and Al surfaces in order to establish the potential adhesive failure mechanisms. However, the JKR studies using commercial based PDMS [poly(dimethylsiloxane)] was fraught with difficulty that were attributed to the additives used in commercial PDMS systems. The authors ...
Date: February 21, 2000
Partner: UNT Libraries Government Documents Department

Formation of Random, RIE-Textured Silicon Surfaces with Reduced Reflection and Enhanced Near IR Absorption

Description: The authors have developed novel metal-assisted texturing processes that have led to optically favorable surfaces for solar cells. Large area ({approximately} 200 cm{sup 2}) uniform texturing has been achieved. The physical dimensions of the chamber limited texturing of even larger wafers. Surface contamination and residual RIE-induced damage were removed by incorporation of a complete RCA clean process followed by wet-chemical etching treatments. RIE-textured solar cells with optimized profiles providing performance comparable to the random, wet-chemically etched cells have been demonstrated. A majority of the texture profiles exhibit an enhanced IQE response in the near IR region.using scanning electron microscope measurements, they carried out a detailed analysis of the microstructure of random RIE-textured surfaces. The random microstructure represents a superposition of sub-{micro}m grating structures with a wide distribution of periods, depths, and profiles as determined by the SEM measurements. These structures were modeled using GSOLVER{trademark} software for periodic patterns. The enhanced IR response from random, RIE-textured surfaces is attributed to enhanced coupling of light into the transmitted diffraction orders. These obliquely propagating diffraction orders generate electron-hole pairs closer to the surface, thus, reducing bulk recombination losses relative to a non-scattering, planar surface with identical hemispherical reflection. The optimized texture and damage removal processes have been applied to large area (100--132 cm{sup 2}) multi-crystalline wafers. initial results have demonstrated improved performance relative to planar, control wafers. However, the texture and solar cell fabrication processes require further optimization in the RCA clean, DRE treatments, and emitter formation in order to fully realize the benefits of the low-reflection ({approximately}1-2%) textured surfaces.
Date: April 1, 2001
Partner: UNT Libraries Government Documents Department

Guidance and methods for satisfying low specific activity material and surface contaminated object regulatory requirements

Description: The US Department of Transportation (DOT) and the US Nuclear Regulatory Commission (NRC) have prepared a comprehensive set of draft guidance for shippers and inspectors to use when applying the newly imposed regulatory requirements for low specific activity (LSA) material and surface contaminated objects (SCOs). These requirements represent significant departures in some areas from the manner in which these materials and objects were regulated by the earlier versions of the regulations. The proper interpretation and application of the regulatory criteria can require a fairly complex set of decisions be made. To assist those trying to apply these regulatory requirements, a detailed set of logic flow diagrams representing decisions related to multiple factors were prepared and included in the draft report for comment on Categorizing and Transporting Low Specific Activity Materials and Surface Contaminated Objects. These logic flow diagrams, as developed, are specific to the US regulations, but were readily adaptable to the IAEA regulations. The diagrams have been modified accordingly and tied directly to specific paragraphs in IAEA Safety Series No. 6. This paper provides the logic flow diagrams adapted to the IAEA regulations, and demonstrates how these diagrams can be used to assist consignors and inspectors in assessing compliance of shipments with the LSA material and SCO regulatory requirements.
Date: February 1, 1998
Creator: Pope, R.B.; Shappert, L.B.; Michelhaugh, R.D.; Boyle, R.W.; Easton, E.P. & Cook, J.R.
Partner: UNT Libraries Government Documents Department

Isotope identification as a part of the decommissioning of San Diego State University`s Texas Nuclear neutron generator

Description: The Department of Physics at San Diego State University has maintained a Neutron Generator facility in room P-32C since the mid 1960`s. This facility has provided students and faculty with a resource for the study of neutron interactions with matter, such as activation analysis, flux determinations, cross section determinations and shielding studies. The model 9500 was built by Texas Nuclear Research in the early 1960`s, and could be used for either photon or neutron generation, depending on the source ions introduced into the accelerator`s plasma bottle and the target material. In February of 1988, the Texas Nuclear Research neutron generator was replaced by a unit manufactured by Kaman Sciences Corporation. The Texas Nuclear unit was then removed and stored for later disassembly and disposal. In the summer of 1993, the neutron generator was disassembled into three large sections consisting of the titanium-tritide target, the oil diffusion pump and the corona shield/accelerator tube assembly. The target was packaged and stored in room P-33A and the other 2 assemblies were wrapped in plastic for storage. In June of 1995 the neutron generator was further disassembled to enable storage in 55 gallon drums and thoroughly surveyed for loose surface contamination. Openings on the disassembled hardware components were closed off using either duct tape or bolted stainless steel flanges to prevent the possible spread of contamination. Significant levels of removable surface contamination could be found on system internal and some external surfaces, up to five hundred thousand disintegrations per minute. Initial analysis of the removable contamination using aluminum absorbers and a Geiger-Meuller tube indicated beta particle or possibly photon emitters with an energy of approximately 180 keV. This apparent radiation energy conflicted with what one would be expected to find, given knowledge of the source material and the possible neutron activated products that would ...
Date: July 1, 1997
Creator: Taylor, D.
Partner: UNT Libraries Government Documents Department

A simplified ALARA approach to demonstration of compliance with surface contaminated object regulatory requirements

Description: The US Department of Transportation (DOT) and the US Nuclear Regulatory Commission (NRC) have jointly prepared a comprehensive set of draft guidance for consignors and inspectors to use when applying the newly imposed regulatory requirements for low specific activity (LSA) material and surface contaminated objects (SCOs). The guidance is being developed to facilitate compliance with the new LSA material and SCO requirements, not to impose additional requirements. These new requirements represent, in some areas, significant departures from the manner in which packaging and transportation of these materials and objects were previously controlled. On occasion, it may be appropriate to use conservative approaches to demonstrate compliance with some of the requirements, ensuring that personnel are not exposed to radiation at unnecessary levels, so that exposures are kept as low as reasonably achievable (ALARA). In the draft guidance, one such approach would assist consignors preparing a shipment of a large number of SCOs in demonstrating compliance without unnecessarily exposing personnel. In applying this approach, users need to demonstrate that four conditions are met. These four conditions are used to categorize non-activated, contaminated objects as SCO-2. It is expected that, by applying this approach, it will be possible to categorize a large number of small contaminated objects as SCO-2 without the need for detailed, quantitative measurements of fixed, accessible contamination, or of total (fixed and non-fixed) contamination on inaccessible surfaces. The method, which is based upon reasoned argument coupled with limited measurements and the application of a sum of fractions rule, is described and examples of its use are provided.
Date: February 1, 1998
Creator: Pope, R.B.; Shappert, L.B.; Michelhaugh, R.D.; Boyle, R.W. & Cook, J.C.
Partner: UNT Libraries Government Documents Department

Assessment of strippable coatings for decontamination and decommissioning

Description: Strippable or temporary coatings were developed to assist in the decontamination of the Three Mile Island (TMI-2) reactor. These coatings have become a viable option during the decontamination and decommissioning (D and D) of both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both vertical and horizontal surfaces. A variety of strippable coatings are available to D and D professionals. However, these products exhibit a wide range of performance criteria and uses. The Hemispheric Center for Environmental Technology (HCET) at Florida International University (FIU) was commissioned to perform a 2-year investigation into strippable coatings. This investigation was divided into four parts: (1) identification of commercially available strippable coating products; (2) survey of D and D professionals to determine current uses of these coatings and performance criteria; (3) design and implementation of a non-radiological testing program to evaluate the physical properties of these coatings; and (4) design and implementation of a radiological testing program to determine decontamination factors and effects of exposure to ionizing radiation. Activities during fiscal year 1997 are described.
Date: January 1, 1998
Creator: Ebadian, M.A.
Partner: UNT Libraries Government Documents Department

Y-12 Plant groundwater Protection Program Groundwater and Surface Water Sampling And Analysis Plan For Calendar Year 1999

Description: This plan provides a description of the groundwater and surface water quality monitoring activities planned for calendar year (CY) 1999 at the U.S. Department of Energy (DOE) Y-12 Plant that will be managed by the Y-12 Plant Environmen~ Safety, and Health Organization through the Y-12 Plant Groundwater Protection Progratn (GWPP). Groundwater and surface water monitoring . during CY 1999 will be petiormed in three hydrogeologic regimes at the Y-12 Plant: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime), and the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Bear Creek and East Fork regimes are located in Bear Creek Valley, and the Chestnut Ridge Regime is located south of the Y-12 Plant (Figure 1). Groundwater and surface water monitoring petiormed under the auspices of the Y-12 Plant GWPP during CY 1999
Date: September 1, 1998
Creator: Jones, S. B.
Partner: UNT Libraries Government Documents Department

Characterizing, for packaging and transport, large objects contaminated by radioactive material having a limited A{sub 2} value

Description: The International Atomic Energy Agency (IAEA) Regulations for the safe packaging and transportation of radioactive materials follow a graded approach to the requirements for both packaging and controls during transport. The concept is that, the lower the risk posed to the people and the environment by the contents, (1) the less demanding are the packaging requirements and (2) the smaller in number are the controls imposed on the transport of the material. There are likely to be a great number of situations arising in coming years when large objects, contaminated with radioactive material having unlimited A{sub 2} values will result from various decommissioning and decontamination (D and D) activities and will then require shipment from the D and D site to a disposal site. Such situations may arise relatively frequently during the cleanup of operations involving mining, milling, feedstock, and uranium enrichment processing facilities. Because these objects are contaminated with materials having an unlimited A{sub 2} value they present a low radiological risk to worker and public safety and to the environment during transport. However, when these radioactive materials reside on the surfaces of equipment and other large objects, where the equipment and objects themselves are not radioactive, the radioactive materials appear as surface contamination and, if the contaminated object is categorized as a surface contaminated object, it would need to be packaged for shipment according to the requirements of the Regulations for SCO. Despite this categorization, alternatives may be available which will allow these contaminants, when considered by themselves for packaging and transport, to be categorized as either (1) a limited quantity of radioactive material to be shipped in an excepted package or (2) low specific activity (LSA) materials to be shipped in an IP-1 package or possibly even shipped unpackaged. These options are discussed in this paper.
Date: February 1, 1998
Creator: Pope, R.B.; Shappert, L.B.; Michelhaugh, R.D.; Cash, J.M. & Best, R.E.
Partner: UNT Libraries Government Documents Department

Colorimetric Method for Beryllium Surface Contamination Detection

Description: To address the need for real-time accurate total beryllium analyses, Savannah River Technology Center Analytical Development Section personnel evaluated and modified a colorimetric screening method developed at Los Alamos National Lab to measure beryllium on surfaces. This method was based on a color complex formed by beryllium and chromium azurol s . SRTC converted this visual method to a quantitative analysis method using spectrophotometric detection. The addition of a cationic surfactant (hexadecyltrimethylammonium bromide, CTAB) to the Be-CAS system shifted the complex absorbance away from the CAS absorbance and allowed for the detection. Assuming complete dissolution and a 10 mL rinse solution volume to remove the beryllium from the wipe, the detection limit was calculated comfortably below the free release limit. The spectrophotometric method was rugged and simple enough that it could be used as a field method.
Date: March 11, 2004
Partner: UNT Libraries Government Documents Department

Industrial Hygiene Concerns during the Decontamination and Decommissioning of the Tokamak Fusion Test Reactor

Description: A significant industrial hygiene concern during the Decontamination and Decommissioning (D and D) of the Tokamak Fusion Test Reactor (TFTR) was the oxidation of the lead bricks' surface, which were utilized for radiation shielding. This presented both airborne exposure and surface contamination issues for the workers in the field removing this material. This paper will detail the various protection and control methods tested and implemented to protect the workers, including those technologies deployed to decontaminate the work surfaces. In addition, those techniques employed to recycle the lead for additional use at the site will be discussed.
Date: January 18, 2002
Creator: Lumia, M.E. & Gentile, C.A.
Partner: UNT Libraries Government Documents Department