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Evaluation of photoneutron production at high energy LINACS

Description: This report describes an estimate of neutron production at a 9 MeV LINAC, and the potential for photoactivation of materials present at the LINAC facility. It was found that only isotopes of U, W, Ta, and Pb had daughters whose activities might be measurable. The LINAC was found to be capable of producing in the neighborhood of 10{sup 10} neutrons/second from these heavy metals, and that subsequent neutron activation might be more of a concern. Monte Carlo simulation of neutron transport and capture in the concrete and steel found in the LINAC vault indicates that {sup 55}Fe may be produced in measurable quantities.
Date: April 24, 1995
Creator: Bell, Z.W.
Partner: UNT Libraries Government Documents Department

Development of filler metals for welding of iron aluminide alloys. Final report

Description: Attempts were made to develop a coating formulation for shielded metal arc (SMA) welding electrodes for iron aluminide alloys. Core wires of various compositions were produced by aspiration casting at ORNL and coating formulation development was conducted by Devasco, Inc. It was found that, except for weld deposit compositions containing less than 10 weight % aluminum, all weld deposits exhibited extensive cold cracking and/or porosity. It was concluded that current coating formulation technology limits successful iron aluminide deposits to less than 10 weight % aluminum.
Date: June 29, 1995
Creator: Goodwin, G. M. & Scott, J. L.
Partner: UNT Libraries Government Documents Department

Advanced technology and manufacturing practices for machining and inspecting metal matrix composites. Final CRADA report for CRADA number Y-1292-0092

Description: Lockheed Martin Energy Systems, Inc. (Energy Systems) and the Lanxide Corporation (Lanxide) negotiated a Cooperative Research and Development Agreement (CRADA) to develop advanced technology and manufacturing practices for machining and inspecting metal matrix composites (MMC). The objective of this CRADA was to develop machining parameters to allow manufacturing of automotive components from MMCs. These parts exhibit a range of shapes and dimensional tolerances and require a large number of machining operations. The common characteristic of the components is the use of the light weight MMC materials to replace heavier materials. This allows smaller and lighter moving parts and supporting structural components thereby increasing fuel mileage. The CRADA was divided into three areas: basic investigation of cutting parameters, establishment of a mock production line for components, and optimization of parameters in the mock facility. This report covers the manufacturing of MMCs and preliminary Phase I testing for silicon carbide having various loading percentages and extensive Phase I testing of cutting parameters on 30% alumina loaded aluminum. On January 26, 1995, a letter from the vice president, technology at Lanxide was issued terminating the CRADA due to changes in business. 9 refs., 18 figs., 3 tabs.
Date: February 26, 1995
Creator: Fell, H.A.; Shelton, J.E.; LaMance, G.M. & Kennedy, C.R.
Partner: UNT Libraries Government Documents Department

Final construction quality assurance report for the Y-12 Industrial Landfill V, Area 2, Oak Ridge, Tennessee

Description: Lockheed Martin Energy Systems (LMES) has finished construction of Area 2 of the Y-12 Plant Industrial Landfill (ILF-V), classified as a Class 2 Landfill. This final Construction Quality Assurance (CQA) Report provides documentation that Area 2 was constructed in substantial compliance with the Tennessee Department of Environment and Conservation (TDEC) approved design, as indicated and specified in the permit drawings, approved changes, and specifications. This report applies specifically to the Area 2 excavation, compacted clay soil liner, geomembrane liner, granular leachate collection layer, protective soil cover, and the leachate collection system. An ``As-Built`` survey was performed and is included. The drawings provide horizontal and vertical information for Area 2, the anchor trench, the leachate collection pipe, the temporary access road, and cross-sections of Area 2. This report provides documentation of the following items: the excavation activities of Area 2; the maximum recompacted coefficient of hydraulic conductivity or permeability of the soil is less than 1 {times} 10{sup {minus}7} centimeters per second (cm/sec); the total thickness of the compacted clay soil liner equals a minimum of 2 feet; a 40 mil impermeable geomembrane (polypropylene) flexible membrane liner (FML) and 16 oz. geotextile fabric was placed in direct contact with the compacted clay soil liner; a 12 inch granular leachate collection layer was installed and covered with a 8 oz. geotextile separation fabric; the installation of the leachate collection piping; and the two foot protective clay soil cover.
Date: November 1, 1996
Creator: Bessom, W.H.
Partner: UNT Libraries Government Documents Department

Analysis of production line motor failure. CRADA final report for CRADA number Y-1293-0215

Description: The Oak Ridge National Laboratory (ORNL) was approached by a Food Products Manufacturer (FPM) to investigate the rapid failure of motors in a manufacturing facility. It was reported that some motors or their bearings were being replaced after as little as four months of service. The deciding symptom for replacement was always high motor vibration. To protect against unscheduled downtime in the middle of a process run, the FPM`s maintenance team removes a motor from service when its vibration level reaches a conservative threshold of approximately 0.4 inches per second. In their experience, motors left in service after reaching this vibration threshold can fail at any time within the time span of the next process run causing significant losses of raw material and production capacity. A peculiar finding of vibration level trend analysis was that at least one motor exhibited cyclic variations with 24-hour periodicity. The vibration level reached a maximum at about 4:00 a.m., ramped down during the day, and then rose again during the night. Another peculiarity was that most of the vibration energy in the affected motors was at the 120 Hz frequency. Since this is twice the 60 Hz line frequency the FPM suspected the vibration was electrically induced. The electric loads at the FPMs plant remain constant during the five days of a continuous production run. Thus, the periodicity of the vibration observed, with its daily peaking at about four am, suggested the possibility of being driven by changes in the electrical power grid external to the plant.
Date: February 10, 1995
Creator: Kueck, J. & Talbott, C.
Partner: UNT Libraries Government Documents Department

How Should We Manage All Those Databases?

Description: In an organization where there are many DBAs working with many instances and databases on many machines with many developers � how do you manage all of this without total chaos? This paper will outline how the central Database Support organization at Lockheed Martin Energy Systems in Oak Ridge, TN manages more than 250 instances on more than 90 systems with a variety of operating systems. This discussion will include how tasks and responsibilities are divided between System DBAs, Application Project DBAs, and developers. The use of standards as well as local routines to maintain the systems will be discussed. Information on the type of communications used to keep the different group informed and up-to-date will also be presented.
Date: October 1, 1998
Creator: Langley, K. E.
Partner: UNT Libraries Government Documents Department

Shake table testing of structural clay tile infilled frames

Description: Two steel frames with structural clay tile infills were tested under simulated seismic loads in both the out-of-plane and in-plane direction. Out-of-plane testing showed that infill panels separate from their bounding frame, and respond at their own natural frequency during a seismic excitation. Due to arching, the panels remain stable. In-plane seismic testing showed similar behavior patterns to previous static testing. The natural frequency was adequately predicted using a piecewise linear equivalent strut analytical method. The structure was then subjected to over one thousand cycles of loading using a sine sweep before failure.
Date: March 8, 1996
Creator: Bennett, R.M.; Fowler, J.J. & Flanagan, R.D.
Partner: UNT Libraries Government Documents Department

Engineering report for the central mercury treatment system

Description: Mercury (Hg) was used at the Oak Ridge Y-12 Plant between 1950 and 1963. This contamination legacy has prompted a series of remedial measures. Since the mid-1980s, a series of engineered projects, maintenance activities, and general improvement in work practices has resulted in a decreasing trend of Hg concentration in East Fork Poplar Creek (EFPC). Some of the Hg in the soils surrounding past Hg- use buildings enters the building sumps which are discharged to EFPC. Overall goal is to reduce the Hg contamination of EFPC to no more than 5 g/day. This project will create the Central Mercy Treatment System to reduce the Hg contribution to EFPC by installing carbon adsorption units to treat the effluent from buildings 9201-4, 9201-5, and 9204-4. Use of carbon adsorption will be the long-term strategy for reduction of Hg in plant effluent.
Date: March 1, 1995
Partner: UNT Libraries Government Documents Department

Discussion paper on applicability of oil and grease analysis for RCRA closure criteria

Description: A site characterization (SC) was performed for the Building 9409-5 Diked Tank Storage Facility. The initial SC indicated areas which had oil and grease levels above the criteria of the currently proposed RCRA closure plan. After further investigation, it was demonstrated that the oil and grease parameter may not be an accurate indication of a release from this facility and should not be included as a contaminant of concern in the closure criteria.
Date: February 1, 1995
Partner: UNT Libraries Government Documents Department

Continuous Holdup Measurements with Silicon P-I-N Photodiodes

Description: We report on the behavior of silicon P-I-N photodiodes used to perform holdup measurements on plumbing. These detectors differ from traditional scintillation detectors in that no high-voltage is required, no scintillator is used (gamma and X rays are converted directly by the diode), and they are considerably more compact. Although the small size of the diodes means they are not nearly as efficient as scintillation detectors, the diodes' size does mean that a detector module, including one or more diodes, pulse shaping electronics, analog-to-digital converter, embedded microprocessor, and digital interface can be realized in a package (excluding shielding) the size of a pocket calculator. This small size, coupled with only low-voltage power requirement, completely solid-state realization, and internal control functions allows these detectors to be strategically deployed on a permanent basis, thereby reducing or eliminating the need for manual holdup measurements. In this paper, we report on the measurement of gamma and X rays from {sup 235}U and {sup 238}U contained in steel pipe. We describe the features of the spectra, the electronics of the device and show how a network of them may be used to improve estimates of inventory in holdup.
Date: May 1, 2002
Creator: Bell, Z.W.; Oberer, R.B.; Williams, J.A.; Smith, D.E. & Paulus, M.J.
Partner: UNT Libraries Government Documents Department

Modeling and Simulation of Microelectrode-Retina Interactions

Description: The goal of the retinal prosthesis project is the development of an implantable microelectrode array that can be used to supply visually-driven electrical input to cells in the retina, bypassing nonfunctional rod and cone cells, thereby restoring vision to blind individuals. This goal will be achieved through the study of the fundamentals of electrical engineering, vision research, and biomedical engineering with the aim of acquiring the knowledge needed to engineer a high-density microelectrode-tissue hybrid sensor that will restore vision to millions of blind persons. The modeling and simulation task within this project is intended to address the question how best to stimulate, and communicate with, cells in the retina using implanted microelectrodes.
Date: November 30, 2002
Creator: Beckerman, M
Partner: UNT Libraries Government Documents Department

Addition of Tomographic Capabilities to NMIS

Description: This paper describes tomographic capabilities for the Nuclear Materials Identification System (NMIS). The tomographic capabilities add weapons component spatial and material properties information that result in a more detailed item signature (template) and provide more information for physical attributes analyses. The Nuclear Materials Identification System (NMIS) is used routinely to confirm the identity of HEU components in sealed containers. It does this through a radiation signature acquired by shining a {sup 252}Cf source through the container and measuring the radiation at four detectors stacked vertically on the other side. This measurement gives a gamma and neutron radiation transmission profile of the weapons component, mixed with the radiation production due to the induced fissions in the fissile materials. This information is sufficient to match an ''unknown'' weapons component signature to a template signature from a reference item when measuring under controlled conditions. Tomography measures the interior of an item by making transmission measurements from all angles around the item, whereas NMIS makes the measurements from a single angle. Figure 1 is a standard example of tomographic reconstruction, the Shepp-Logan human brain phantom. The measured quantity is attenuation so high values (white) are highly attenuating areas.
Date: March 11, 2003
Creator: Mullens, J. A.
Partner: UNT Libraries Government Documents Department

Explosive Potential Analysis of AB Process-Final Report

Description: A need arose to define the hazards associated with the operation of a process. The process involved the evolution of a hydrogen gas stream from thermal decomposition of uranium hydride at approximately 400 C into the interior of a purged argon-filled glove box. Specific hazards of interest included the potential reaction severity of the evolved hydrogen with atmospheric oxygen, either downstream in the vent system or inside the box in the event of serious air inleakage. Another hazard might be the energetic reaction of inleaked air with the hot uranium and uranium hydride powder bed, possibly resulting in the dispersion of powders into an air atmosphere and the rapid combustion of the powders. This was approached as a problem in calculational simulation. Given the parameters associated with the process and the properties of the glove box system, certain scenarios were defined and the potential for flammable or detonation reactions estimated. Calculation tools included a comprehensive fluid dynamics code, a spreadsheet, a curve-fitting program, an equation solver, and a thermochemistry software package. Results are reported which suggest that the process can be operated without significant hazard to operators or significant damage to equipment, assuming that operators take account of potential upset scenarios.
Date: October 12, 2001
Creator: Bullock, J.S.; Giles, G.E. jr.; Wendel, M.W. & Sulfredge, C.D.
Partner: UNT Libraries Government Documents Department

Monte Carlo Modeling of High-Energy Film Radiography

Description: High-energy film radiography methods, adapted in the past to performing specific tasks, must now meet increasing demands to identify defects and perform critical measurements in a wide variety of manufacturing processes. Although film provides unequaled resolution for most components and assemblies, image quality must be enhanced with much more detailed information to identify problems and qualify features of interest inside manufactured items. The work described is concerned with improving current 9 MeV nondestructive practice by optimizing the important parameters involved in film radiography using computational methods. In order to follow important scattering effects produced by electrons, the Monte Carlo N-Particle (MCNP) transport code was used with advanced, highly parallel computer systems. The work has provided a more detailed understanding of latent image formation at high X-ray energies, and suggests that improvements can be made in our ability to identify defects and to obtain much more detail in images of fine features.
Date: March 28, 2003
Creator: Miller, A. C., Jr.; Cochran, J.L. & Lamberti, V.E.
Partner: UNT Libraries Government Documents Department

Enhanced Trace-Fiber Color Discrimination by Electrospray Ionization Mass Spectrometry: A Quantitative and Qualitative Tool for the Analysis of Dyes Extracted from Sub-millimeter Nylon Fibers

Description: The application of electrospray-ionization mass spectrometry (ESI-MS) to trace-fiber color analysis is explored using acidic dyes commonly employed to color nylon-based fibers, as well as extracts from dyed nylon fibers. Qualitative information about constituent dyes and quantitative information about the relative amounts of those dyes present on a single fiber become readily available using this technique. Sample requirements for establishing the color-identity of different samples (i.e., comparative trace-fiber analysis) are shown to be sub-millimeter. Absolute verification of dye-mixture identity (beyond the comparison of molecular weights derived from ESI-MS) can be obtained by expanding the technique to include tandem mass spectrometry (ESI-MS/MS). For dyes of unknown origin, the ESI-MS/MS analyses may offer insights into the chemical structure of the compound--information not available from chromatographic techniques alone. This research demonstrates that ESI-MS is viable as a sensitive technique for distinguishing dye constituents extracted from a minute amount of trace fiber evidence. A protocol is suggested to establish/refute the proposition that two fibers--one of which is available in minute quantity only--are of the same origin.
Date: September 26, 2002
Partner: UNT Libraries Government Documents Department

The GraFIC TM Facility Management Software [TM = Trademark Symbol]

Description: The Graphical Facility Information System{trademark} (GraFIC{trademark}) is an intelligent facility and information management system that provides near real time, verifiable status of safeguarded materials in a nuclear storage facility. GraFIC{trademark} is a versatile software package that is designed to operate in a distributed computing environment and to provide item and facility activity information to an unlimited number of authorized clients. Recent extensions to GraFIC{trademark} include the ability to link graphical entities to multimedia documents, interfaces to multiple material control and accountability systems, and alternate data entry and operator interaction mechanisms. Relevant multimedia documents such as still images and iPIX{trademark} immersive images can be summoned on demand from their icons on floor plans. An iPIX{trademark} image server, equipped with the appropriate sensors can signal GraFIC{trademark} that an event that warrants the review of a series of saved iPIX{trademark} images has occurred. GraFIC{trademark} provides mechanisms for presenting information obtained from sensor-based monitoring systems and/or other information systems in a common, easy-to-use graphical format. GraFIC{trademark} was initially integrated with the Continuous Automated Vault Inventory System's (CAVIS{trademark} ) suite of rugged, low-cost sensors that remotely monitor the physical and/or assigned attributes associated with stored nuclear materials. GraFIC{trademark} can now interface with the ReflectoActive Seals{trademark} (RASeals) System. The framework designed for the RASeals interface is suitable for integrating with other systems, such as SmartShelf{trademark} . GraFIC{trademark} can import existing data for stored material from other information systems. By retrieving existing information from other information systems, the expense, effort, and possible inaccuracies associated with manual entry are eliminated. Another data entry method involves offloading the data from the hand held terminals/barcode readers used by operators on the warehouse floor. GraFIC{trademark} also contains facility management tools needed for the day-to-day management of storage and other facilities and gives facility managers and personnel instant access to the information ...
Date: June 2002
Creator: Younkin, J. R.; Dunigan, J. J.; Gaby, J. E.; Hickerson, T. W. & Pickett, C. A.
Partner: UNT Libraries Government Documents Department

Calendar Year 2002 Groundwater Monitoring Report, U.S. Department of Energy Y-12 National Security Complex, Oak Ridge, Tennessee

Description: This report contains the groundwater and surface water monitoring data that were obtained during calendar year (CY) 2002 at the U.S. Department of Energy (DOE) Y-12 National Security Complex (hereafter referenced as Y-12) on the DOE Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee. The CY 2002 monitoring data were obtained from groundwater and surface water sampling locations in three hydrogeologic regimes at Y-12. The Bear Creek Hydrogeologic Regime (Bear Creek Regime) encompasses a section of Bear Creek Valley (BCV) between the west end of Y-12 and the west end of the Bear Creek Watershed (directions are in reference to the Y-12 grid system). The Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime) encompasses the Y-12 industrial facilities and support structures in BCV. The Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime) encompasses a section of Chestnut Ridge south of Y-12. The sections of this report provide details regarding the CY 2002 groundwater and surface water monitoring activities in the Bear Creek, East Fork, and Chestnut Ridge Regimes. Section 2 describes the monitoring programs implemented by the Y-12 GWPP and BJC during CY 2002. Section 3 identifies the sampling locations in each hydrogeologic regime and the corresponding sampling frequency during CY 2002, along with the associated quality assurance/quality control (QA/QC) sampling. Section 4 describes groundwater and surface water sample collection and Section 5 identifies the field measurements and laboratory analytes for each sampling location. Section 6 outlines the data management protocols and data quality objectives (DQOs). Section 7 describes the groundwater elevation monitoring in each regime during CY 2002 and Section 8 lists the documents cited for more detailed operational, regulatory, and technical information.
Date: March 31, 2003
Partner: UNT Libraries Government Documents Department

A Generalized Finite Source Calibration Factor: A Natural Improvement to the Finite Source Correction Factor for Uranium Holdup Measurements

Description: This paper proposes refinements to the finite source correction factor used in holdup measurements. Specifically it focuses on a more general method to estimate the average detector response for a finite source. This proposed method for the average detector response is based directly on the Generalized Geometry Holdup (GGH) assay method. First, the finite source correction factor as originally proposed is reviewed in this paper. Following this review the GGH assay method is described. Lastly, a new finite area calibration factor based on GGH is then proposed for finite point and line sources. As an alternative to the direct use of the finite arca calibration factor, finite source correction factors are also derived from this calibration factor. This new correction factor can be used in a manner similar to the finite source correction factor as currently implemented.
Date: January 28, 2003
Creator: Gunn, C.A.; Oberer, R.B.; chiang, L.G. & Ceo, R.N.
Partner: UNT Libraries Government Documents Department

Geophysical Surveys of a Known Karst Feature, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

Description: Geophysical data were acquired at a site on the Oak Ridge Reservation, Tennessee to determine the characteristics of a mud-filled void and to evaluate the effectiveness of a suite of geophysical methods at the site. Methods that were used included microgravity, electrical resistivity, and seismic refraction. Both microgravity and resistivity were able to detect the void as well as overlying structural features. The seismic data provide bedrock depth control for the other two methods, and show other effects that are caused by the void.
Date: December 1, 1998
Creator: Doll, W.E.; Nyquist, J.E.; Carpenter, P.J.; Kaufmann, R.D. & Carr, B.J.
Partner: UNT Libraries Government Documents Department

HotSpotter? Neutron/Gamma Detector

Description: The HotSpotter{trademark} Neutron/Gamma Detector combines in a single detecting module high sensitivity to gamma rays up to 3 MeV and sensitivity to neutrons. Using a 15 mm cubic CdWO{sub 4} (cadmium tungstate) crystal mounted on a 25 mm photomultiplier, the instrument realizes a factor of 5 increased photopeak efficiency over NaI(Tl) at 1 MeV, and a factor of 2 improvement over CsI(Tl). The addition of a 0.5 mm layer of {sup 10}B- impregnated epoxy covering the crystal provides neutron sensitivity without sacrificing gamma ray spectroscopic characteristics. Neutrons are detected by the presence of the 478 keV gamma from the {sup 10}B(n,{alpha}){sup 7}Li* reaction. In this paper, we describe the electronics and software of the instrument, and some of its characteristics.
Date: April 1, 2003
Creator: Bell, Z. W.
Partner: UNT Libraries Government Documents Department

Criteria for the safe storage of lithium metal and lithium compounds at the Y-12 Plant

Description: Considerable quantities of lithium-based materials are being generated as a result of the nuclear weapons disassembly process. The lithium from these materials, in the form of lithium hydride (LiH) and lithium deuteride (LiD), is enriched in the lithium-6 ({sup 6}Li) isotope and is considered to be an accountable nuclear material. These materials are neither radioactive nor fissile, but they are integral components of nuclear weapons. The LiD functions as a fuel for thermonuclear fusion and the LiH functions as a neutron moderator. Current plans are to store such materials in a suitable chemical form until they are needed for building future weapons or for other undefined uses. Because no domestic capability exists for producing enriched {sup 6}Li and because {sup 6}Li is an integral component of nuclear weapons, it must be stored safely, securely, and in an environmentally compliant form.
Date: July 1, 1995
Creator: Cox, S.O.
Partner: UNT Libraries Government Documents Department

Y-12 Plant Stratospheric Ozone Protection plan

Description: The Y-12 Plant staff is required by Lockheed Martin Energy Systems (Energy Systems) (formerly Martin Marietta Energy Systems) standard ESS-EP-129 to develop and implement a Stratospheric Ozone Protection Program which will minimize emissions of ozone-depleting substances to the environment and maximize the use of ozone-safe alternatives in order to comply with Title VI of the 1990 Clean Air Act (CAA) Amendments and the implementing regulations promulgated by the Environmental Protection Agency (EPA). This plan describes the requirements, initiatives, and accomplishments of the Y-12 Plant Stratospheric Ozone Protection Program.
Date: September 1, 1995
Partner: UNT Libraries Government Documents Department

Resource Conservation and Recovery Act (RCRA) Closure Plan Summary for Interim reasctive Waste Treatment Area (IRWTA)

Description: This closure plan has been prepared for the interim Reactive Waste Treatment Area (IRWT'A) located at the Y-12 Pkmt in oak Ridge, Tennessee (Environmental Protection Agency [EPA] Identification TN 389-009-0001). The actions required to achieve closure of the IRWTA are outlined in this plan, which is being submitted in accordance with Tennessee Ruie 1200- 1-1 1-.0S(7) and Title 40, Code of Federal Regulations (CFR), Part 265, Subpart G. The IRWTA was used to treat waste sodium and potassium (NaK) that are regulated by the Resource Conservation and Recovery Act (RCRA). The location of the IRWT'A is shown in Figures 1 and 2, and a diagram is shown in Figure 3. This pkm details all steps that wdi be petiormed to close the IRWTA. Note that this is a fmai ciosure.and a diagram is shown in Figure 3. This pkm details all steps that wdi be petiormed to close the IRWTA. Note that this is a fmai ciosure.
Date: July 1, 1997
Creator: Collins, E.T.
Partner: UNT Libraries Government Documents Department