Crystalline Beam Properties as Predicted for the Storage Ring ASTRID and TSR (open access)

Crystalline Beam Properties as Predicted for the Storage Ring ASTRID and TSR

Employing a previously developed formalism 1, we have performed ground-state and melting calculations of the expected crystalline beams in ion storage rings ASTRID and TSR.
Date: March 1, 1995
Creator: Wei, J.; Li, X. P. & Sessler, Andrew M.
Object Type: Article
System: The UNT Digital Library
ESF BLAST DESIGN ANALYSIS (open access)

ESF BLAST DESIGN ANALYSIS

The purpose and objective of this design analysis are to develop controls considered necessary and sufficient to implement the requirements for the controlled drilling and blasting excavation of operations support alcoves and test support alcoves in the Exploratory Studies Facility (ESF). The conclusions reached in this analysis will flow down into a construction specification ensuring controlled drilling and blasting excavation will be performed within the bounds established here.
Date: March 13, 1995
Creator: Fitch, E. F.
Object Type: Report
System: The UNT Digital Library
PERMANENT ROCKBOLT AND TEMPORARY CHANNEL INTERACTION ANALYSIS (open access)

PERMANENT ROCKBOLT AND TEMPORARY CHANNEL INTERACTION ANALYSIS

The purpose of this analysis is to evaluate the interaction of a quality assurance (QA) classified item (QA-1 and QA-5) with an item of temporary function (QA: NONE), in accordance with Requirement 8 of the Determination of Importance Evaluation (DIE) (Reference Section 5.1). This interaction analysis will be done by determining the forces on ''Williams'' rockbolts transferred from temporary function channels under maximum capacity loads, and ensuring that these loads do not compromise the critical characteristics of these rockbolts.
Date: March 14, 1995
Creator: Keifer, J. & Taylor, M.
Object Type: Report
System: The UNT Digital Library
Contaminant Distributions at Typical U.S. Uranium Milling Facilities and Their Effect on Remedial Action Decisions (open access)

Contaminant Distributions at Typical U.S. Uranium Milling Facilities and Their Effect on Remedial Action Decisions

Past operations at uranium processing sites throughout the US have resulted in local contamination of soils and ground water by radionuclides, toxic metals, or both. Understanding the origin of contamination and how the constituents are distributed is a basic element for planning remedial action decisions. This report describes the radiological and nonradiological species found in ground water at a typical US uranium milling facility. The report will provide the audience with an understanding of the vast spectrum of contaminants that must be controlled in planning solutions to the long-term management of these waste materials.
Date: March 1, 1995
Creator: Hamp, Steve; Jackson, Timothy J. & Dotson, Patrick W.
Object Type: Report
System: The UNT Digital Library
Protective clothing based on permselective membrane and carbon adsorption (open access)

Protective clothing based on permselective membrane and carbon adsorption

The objective of this program is to develop improved protective clothing for use by workers engaged in decomissioning and decontamination of former DOE sites. The proposed technology concerns a new protective clothing fabric that combines a permselective membrane layer (for water transmission and breathability) with a sorptive layer.
Date: March 1, 1995
Creator: Baker, R.
Object Type: Article
System: The UNT Digital Library
Scale-up of miscible flood processes for heterogeneous reservoirs. Second annual report (open access)

Scale-up of miscible flood processes for heterogeneous reservoirs. Second annual report

Progress is reported for a comprehensive investigation of the scaling behavior of gas injection processes in heterogeneous reservoirs. The interplay of phase behavior, viscous fingering, gravity segregation, capillary imbibition and drainage, and reservoir heterogeneity is examined in a series of simulations and experiments. Use of streamtube to model multiphase flow is demonstrated to be a fast and accurate approach for displacements that are dominated by reservoir heterogeneity. The streamtube technique is particularly powerful for multiphase compositional displacements because it represents the effects of phase behavior with a one-dimensional flow and represents the effects of heterogeneity through the locations of streamtubes. A new approach for fast calculations of critical tie-lines directly from criticality conditions is reported. A global triangular structure solution for four-component flow systems, whose tie-lies meet at the edge of a quaternary phase diagram or lie in planes is presented. Also demonstrated is the extension of this solution to multicomponent systems under the same assumptions. The interplay of gravity, capillary and viscous forces on final residual oil saturation is examined experimentally and theoretically. The analysis of vertical equilibrium conditions for three-phase gravity drainage shows that almost all oil can be recovered from the top part of a reservoir. The …
Date: March 1, 1995
Creator: Orr, F. M., Jr.
Object Type: Report
System: The UNT Digital Library
Tracer studies of radionuclide migration in fractured rock at a scale of 1 meter (open access)

Tracer studies of radionuclide migration in fractured rock at a scale of 1 meter

The Large Block Tracer Test is a series of experiments to study the migration of radionuclides through fractures in rock at the scale of one meter. The separate effects to be considered are sorption onto minerals within the rock matrix; diffusion of radionuclide species through the rock matrix, diffusion and hydrodynamic dispersion within the fracture; and the effect of heterogeneity in the fluid flow field (also known as macro dispersion or channeling). The rock fractures to be used have natural fractures or artificial fractures with engineered heterogeneity. These tracer experiments will provide data with well-defined geometry and conditions for use in code validation. The experiments also provide an experimental framework to test inverse methods. Results are presented for a series of migration experiments using conservative tracers in artificial fractures with near parallel plane and near wedge-shaped fractures. The results are compared with those predicted with transport code TRACR3D. The fracture is treated as an equivalent porous medium with a ``cubic law`` permeability and a porosity that is proportional to the aperture. The results show good agreement, both between experimental results and those predicted by TRACR3D, but also between the distribution of the dye tracer in the fracture and the elution …
Date: March 1, 1995
Creator: Rundberg, R. S.; Travis, B.; Vandergraaf, T. T. & Drew, D. J.
Object Type: Article
System: The UNT Digital Library
Designing radiation protection signs (open access)

Designing radiation protection signs

Entry into hazardous areas without the proper protective equipment is extremely dangerous and must be prevented whenever possible. Current postings of radiological hazards at the Rocky Flats Environmental Technology Site (RFETS) do not incorporate recent findings concerning effective warning presentation. Warning information should be highly visible, quickly, and easily understood. While continuing to comply with industry standards (e.g., Department of Energy (DOE) guidelines), these findings can be incorporated into existing radiological sign design, making them more effective in terms of usability and compliance. Suggestions are provided for designing more effective postings within stated guidelines.
Date: March 1, 1995
Creator: Rodriguez, M. A. & Richey, C. L.
Object Type: Article
System: The UNT Digital Library
Evaluation of design options for improving the energy efficiency of an environmentally safe domestic refrigerator-freezer (open access)

Evaluation of design options for improving the energy efficiency of an environmentally safe domestic refrigerator-freezer

In order to reduce greenhouse emissions from power plants and respond to regulatory actions arising from the National Appliance Energy Conservation Act (NAECA), several design options were investigated for improving the energy efficiency of a conventionally designed, domestic refrigerator-freezer. The options, such as improved cabinet insulation and high-efficiency compressor and fans, were incorporated into a prototype refrigerator-freezer cabinet and refrigeration system to produce a unit that is superior from an environmental viewpoint due to its lower energy consumption and the use of refrigerant HFC-134a as a replacement for CFC-12. Baseline energy performance of the original 1993 production refrigerator-freezer, along with cabinet heat load and compressor calorimeter test results, were extensively documented to provide a firm basis for experimentally measured energy savings. A detailed refrigerator system computer model was used to evaluate the energy savings for several design modifications that, collectively, could achieve a targeted energy consumption of 1.00 kWh/d for a 20 ft{sup 3} (570 l) top-mount, automatic-defrost, refrigerator-freezer. The energy consumption goal represents a 50% reduction in the 1993 NAECA standard for units of this size. Following the modeling simulation, laboratory prototypes were fabricated and tested to experimentally verify the analytical results and aid in improving the model in …
Date: March 1, 1995
Creator: Vineyard, E. A.; Sand, J. R. & Bohman, R. H.
Object Type: Article
System: The UNT Digital Library
The U.S. Regulatory Framework for Long-Term Management of Uranium Mill Tailings (open access)

The U.S. Regulatory Framework for Long-Term Management of Uranium Mill Tailings

The US established the regulatory structure for the management, disposal, and long-term care of uranium mill tailings in 1978 with the passage of the Uranium Mill Tailings Radiation Control Act (UMTRCA) (Pub. L. 95-604). This legislation has governed the cleanup and disposal of uranium tailings at both inactive and active sites. The passage of the UMTRCA established a federal regulatory program for the cleanup and disposal of uranium mill tailings in the US. This program involves the DOE, the NRC, the EPA, various states and tribal governments, private licensees, and the general public. The DOE has completed surface remediation at 14 sites, with the remaining sites either under construction or in planning. The DOE`s UMTRA Project has been very successful in dealing with public and agency demands, particularly regarding disposal site selection and transportation issues. The active sites are also being cleaned up, but at a slower pace than the inactive sites, with the first site tentatively scheduled for completion in 1996.
Date: March 1995
Creator: Smythe, Clinton; Bierley, Denise & Bradshaw, Michael
Object Type: Article
System: The UNT Digital Library
Engineering Solutions to the Long-Term Stabilization and Isolation of Uranium Mill Tailings in the United States (open access)

Engineering Solutions to the Long-Term Stabilization and Isolation of Uranium Mill Tailings in the United States

Engineering solutions to the safe and environmentally protective disposal and isolation of uranium mill tailings in the US include many factors. Cover design, materials selection, civil engineering, erosive forces, and cost effectiveness are only a few of those factors described in this paper. The systems approach to the engineering solutions employed in the US is described, with emphasis on the standards prescribed for the Uranium Mill Tailings Remedial Action Project. Stabilization and isolation of the tailings from humans and the environment are the primary goals of the US uranium mill tailings control standards. The performance of cover designs with respect to water infiltration, radon exhalation, geotechnical stability, erosion protection, human and animal intrusion prevention, and longevity are addressed. The need for and frequency of surveillance efforts to ensure continued disposal system performance are also assessed.
Date: March 1, 1995
Creator: Sanders, Donald R. & Lommler, John C.
Object Type: Report
System: The UNT Digital Library
Development of an Auditable Safety Analysis in Support of a Radiological Facility Classification (open access)

Development of an Auditable Safety Analysis in Support of a Radiological Facility Classification

In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of …
Date: March 1, 1995
Creator: Kinney, Mike D. & Young, Bennett
Object Type: Article
System: The UNT Digital Library
Three-dimensional subsurface imaging synthetic aperture radar (open access)

Three-dimensional subsurface imaging synthetic aperture radar

The objective of this applied research and development project is to develop a system known as `3-D SISAR`. This system consists of a ground penetrating radar with software algorithms designed for the detection, location, and identification of buried objects in the underground hazardous waste environments found at DOE storage sites. Three-dimensional maps of the object locations will be produced which can assist the development of remediation strategies and the characterization of the digface during remediation operations. It is expected that the 3-D SISAR will also prove useful for monitoring hydrocarbon based contaminant migration after remediation. The underground imaging technique being developed under this contract utilizes a spotlight mode Synthetic Aperture Radar (SAR) approach which, due to its inherent stand-off capability, will permit the rapid survey of a site and achieve a high degree of productivity over large areas. When deployed from an airborne platform, the stand-off techniques is also seen as a way to overcome practical survey limitations encountered at vegetated sites.
Date: March 1, 1995
Creator: Moussally, G. J.
Object Type: Article
System: The UNT Digital Library
ECR plasma-assisted deposition of Al{sub 2}O{sub 3} and dispersion-strengthened AlO{sub 2} (open access)

ECR plasma-assisted deposition of Al{sub 2}O{sub 3} and dispersion-strengthened AlO{sub 2}

Electron cyclotron resonance (ECR) O{sub 2} plasmas, in conjunction with electron-beam evaporation of Al, were used to grow thick AlO{sub x} films were varying but controlled composition and microstructure. The ion energy was varied from 30 to 190 eV, and growth temperatures varied from 35{degrees}C to 400{degrees}C. The ECR-film compositions were varied from AlO{sub 0.1} to Al{sub 2}O{sub 3} by controlling the plasma parameters and Al deposition rate. The Al-rich alloys exhibited a fine-grain (10-100 nm) fcc Al microstructure with {gamma}-Al{sub 2}O{sub 3} precipitates ({approximately}1 nm), similar to that found in the gigapascal-strength O-implanted Al. The measured hardness of the ECR Al-O alloys ({approximately}3 GPa) was also similar to the ion-implanted alloys which implies that the yield strength of the ECR material is {approximately}1 GPa. Moreover, the Al-O alloys retain much of the elasticity of the Al metal matrix. As-deposited stoichiometric Al{sub 2}O{sub 3} samples grown with an applied bias of -140 to -160 V at 400{degrees}C were fine-grain polycrystalline {gamma}-Al{sub 2}O{sub 3}. The amorphous films crystallized into the {gamma}-Al{sub 2}O{sub 3} phase upon vacuum annealing to 800{degrees}C.
Date: March 1, 1995
Creator: Barbour, J. C.; Follstaedt, D. M. & Myers, S. M.
Object Type: Article
System: The UNT Digital Library
Applications of Atomistic Simulation to Radioactive and Hazardous Waste Glass Formulation Development (open access)

Applications of Atomistic Simulation to Radioactive and Hazardous Waste Glass Formulation Development

Glass formulation development depends on an understanding of the effects of glass composition on its processibility and product quality. Such compositional effects on properties in turn depend on the microscopic structure of the glass. Historically, compositional effects on macroscopic properties have been explored empirically, e.g., by measuring viscosity at various glass compositions. The relationship of composition to structure has been studied by microstructural experimental methods. More recently, computer simulation has proved a fruitful complement to these more traditional methods of study. By simulating atomic interaction over a period of time using the molecular dynamics method, a direct picture of the glass structure and dynamics is obtained which can verify existing concepts as well as permit ``measurement`` of quantities inaccessible to experiment. Atomistic simulation can be of particular benefit in the development of waste glasses. As vitrification is being considered for an increasing variety of waste streams, process and product models are needed to formulate compositions for an extremely wide variety of elemental species and composition ranges. The demand for process and product models which can predict over such a diverse composition space requires mechanistic understanding of glass behavior; atomistic simulation is ideally suited for providing this understanding. Moreover, while simulation …
Date: March 1, 1995
Creator: Kielpinski, A. L.
Object Type: Article
System: The UNT Digital Library
Simulations of metal dissolution and corrosion. Final report, January 1993-June 1994 (open access)

Simulations of metal dissolution and corrosion. Final report, January 1993-June 1994

There has been considerable interest in microscopic aspects of material removal processes in fields such as corrosion, erosion, evaporation, battery technology, electropolishing, and semiconductor etching. Reports of theoretical work related to many of these problems can be found in the literature although metal dissolution is a noticeable exception. Critical issues common to all dissolution reactions include the relationship between the surface morphology and the driving term (e.g. potential, concentration, temperature); the role of surface active sites, dislocations, and other heterogeneities to the dissolution kinetics; and the influence of surface diffusion We have shown that microscopic analysis of electrochemically dissolving metal surfaces via computer simulations can lead to a fundamental understanding of the relationship between surface morphology and dissolution kinetics. Microscopic information on surface processes is not contained in phenomenological equations such as the Butler-Volmer equation, which is commonly used to describe electrode dissolution. In particular, we find that the surface roughness and, consequently, the number of surface active sites, are determined by thermodynamic parameters such as the applied electrode potential. The morphology of surfaces has been shown to be an essential aspect of kinetic processes such as crystal growth and mineral dissolution. Electrochemical processes, however, are fundamentally different in that …
Date: March 1, 1995
Creator: Searson, P. C.
Object Type: Report
System: The UNT Digital Library
Material selection for Multi-Function Waste Tank Facility tanks (open access)

Material selection for Multi-Function Waste Tank Facility tanks

This paper briefly summarizes the history of the materials selection for the US Department of Energy`s high-level waste carbon steel storage tanks. It also provides an evaluation of the materials for the construction of new tanks at the evaluation of the materials for the construction of new tanks at the Multi-Function Waste Tank Facility. The evaluation included a materials matrix that summarized the critical design, fabrication, construction, and corrosion resistance requirements: assessed. each requirement: and cataloged the advantages and disadvantages of each material. This evaluation is based on the mission of the Multi-Function Waste Tank Facility. On the basis of the compositions of the wastes stored in Hanford waste tanks, it is recommended that tanks for the Multi-Function Waste Tank Facility be constructed of ASME SA 515, Grade 70, carbon steel.
Date: March 1, 1995
Creator: Larrick, A. P.; Blackburn, L. D.; Brehm, W. F.; Carlos, W. C.; Hauptmann, J. P.; Danielson, M. J. et al.
Object Type: Article
System: The UNT Digital Library
Evaluation and qualification of environmentally conscious manufacturing processes for commercial and military applications (open access)

Evaluation and qualification of environmentally conscious manufacturing processes for commercial and military applications

Environmental regulations are encouraging the development of new environmentally conscious manufacturing (ECNP processes. However, the quality and reliability of these processes and hardware produced must be understood prior to implementing these new technologies in factories. Furthermore, military hardware fabrication is governed by standards and specifications that frequently mandate the use of older, less environmentally friendly processes or materials, or prohibit the use of new ECM processes without advance military approvaL Sandia National Laboratories, with industrial and military partners, have developed methodologies for evaluating and qualifying new ECM processes for military and commercial applications, and have piloted these methodologies in qualifying new, low-residue soldering technologies and materials.
Date: March 1, 1995
Creator: Anderson, D. J.; Cranwell, R. M.; Iman, R. & Van Buren, P. D.
Object Type: Article
System: The UNT Digital Library
Graphical representation of robot grasping quality measures (open access)

Graphical representation of robot grasping quality measures

There are multiple solutions to the values of the finger forces of an object held by a multi-fingered hand. An objective function, is used in conjunction with the frictional and geometric constraints of the grasp to give a unique set of finger force values. The selection o the objective function in determining the finger forces is dependent on the type of grasp required, the material properties of the object, and the limitations of the robot fingers. In this paper several optimization functions are studied and their merits highlighted. A graphical representation of the finger force values and the objective function is introduced that enable one in selecting and comparing various grasping configurations. The impending motion of the object at different torque and finger force values are determined by observing the Normalized coefficient of friction plots.
Date: March 1, 1995
Creator: Varma, V. K. & Tasch, U.
Object Type: Article
System: The UNT Digital Library
Stability measurements on a 1-T high temperature superconducting magnet (open access)

Stability measurements on a 1-T high temperature superconducting magnet

A high temperature superconducting magnet based on Bi-2223 conductor was built at the American Superconductor Corporation. The magnet was constructed by a react and wind technique using conductors made from a metallic precursor process. It was a winding ID of 25.4 mm, OD of 87.6 mm, and height of 107.3 mm. A heater, two thermometers, and several voltage taps were built into the high field region of the magnet for stability measurements. The magnet generates 1.1 T central field at 4.2 K when operating at 1 {mu}V/cm over the entire conductor length, including all the joints. Stability measurements were performed in background fields up to 2.5 T from 4.2 K to 77 K. Stability margins more than 2 orders of magnitude higher than a low temperature superconductor were observed.
Date: March 1, 1995
Creator: Lue, J. W.; Dresner, L.; Schwenterly, S. W.; Aized, D.; Campbell, J. M. & Schwall, R. E.
Object Type: Article
System: The UNT Digital Library
Development of an automated fuzing station for the future armored resupply vehicle (open access)

Development of an automated fuzing station for the future armored resupply vehicle

The US Army is developing the Advanced Field Artillery System (SGSD), a next generation armored howitzer. The Future Armored Resupply Vehicle (FARV) will be its companion ammunition resupply vehicle. The FARV with automate the supply of ammunition and fuel to the AFAS which will increase capabilities over the current system. One of the functions being considered for automation is ammunition processing. Oak Ridge National Laboratory is developing equipment to demonstrate automated ammunition processing. One of the key operations to be automated is fuzing. The projectiles are initially unfuzed, and a fuze must be inserted and threaded into the projectile as part of the processing. A constraint on the design solution is that the ammunition cannot be modified to simplify automation. The problem was analyzed to determine the alignment requirements. Using the results of the analysis, ORNL designed, built, and tested a test stand to verify the selected design solution.
Date: March 1, 1995
Creator: Chesser, J. B.; Jansen, J. F.; Lloyd, P. D. & Varma, V. K.
Object Type: Article
System: The UNT Digital Library
Hydrogen Evolution and Sludge Suspension During the Preparation of the First Batch of Sludge at the Savannah River Site (open access)

Hydrogen Evolution and Sludge Suspension During the Preparation of the First Batch of Sludge at the Savannah River Site

The first batch of High Level Radioactive Sludge for the Defense Waste Processing Facility is being prepared in two 4.9 million liter waste tanks. The preparation involves removing water soluble salts by washing (water addition, sludge suspension, settling and decantation). Sludge suspension is accomplished using long shafted slurry pumps that are mounted on rotating turntables. During the sludge suspension runs in 1993 and 1994, the slurry pumps` cleaning radius was determined to be less than that expected from previous determinations using synthetic sludge in a full size waste tank mockup. Hydrogen concentrations in the tanks` vapor space were monitored during the sludge suspension activities. As expected, the initial agitation of the sludge increased the hydrogen concentration, however, with the controls in place the hydrogen concentration was maintained below seven percent of the lower flammability limit
Date: March 1, 1995
Creator: Hay, M. S. & Lee, E. D.
Object Type: Article
System: The UNT Digital Library
Tritium Processing and Containment Practices at the Savannah River Site (open access)

Tritium Processing and Containment Practices at the Savannah River Site

This report emphasizes the features of the United States Tritium Facility operation at the Savannah River Site. It outlines the buildings that represent the facility operating basis. It explores areas where new technology and proven methods of operation developed at the Site have made dramatic environmental and facility work enhancements over the last several years. These enhancements should be consideration for future facility designs and for any current tritium missions.
Date: March 1, 1995
Creator: Buley, R. D.; Green, D. J. & Metzler, J.
Object Type: Article
System: The UNT Digital Library
Development of density and temperature profile diagnostics for ICF targets. Final report, September 30, 1993--December 31, 1994 (open access)

Development of density and temperature profile diagnostics for ICF targets. Final report, September 30, 1993--December 31, 1994

In the authors` research for the period of September 30, 1993 through December 31, 1994, they have upgraded their equipment in anticipation of the restart of the upgraded lasers at the University of Rochester Laboratory for Laser Energetics/National Laser User Facility (LLE/NLUF) and elsewhere. As a direct result of cooperation with Dr. Paul Jaanimagi of LLE, they have modified the cathode on a LLE-designed front-illuminated streak camera so as to operate over a wavelength range extending from the x-ray ({ge} 0.3 nm) into the vacuum ultraviolet (> 100 nm) spectral regions. They have accomplished this with (coated) screen cathodes which permit the photoelectrons to freely penetrate through the openings after emission from the mesh surfaces. Such cathodes were studied, compared and optimized. In anticipation of the development of these long-wavelength photocathodes, they assembled and tested a xuv flat-field streak spectrograph using a varied-spacing grating and covering the 4--30 nm wavelength region. They successfully obtained spectra of highly-ionized boron and carbon. They have also installed a new 300 grooves/mm, 4.2{degree} blazed grating in their ``McPig`` microchannel plate equipped grazing incidence spectrograph, and obtained test spectra extending from 3 to 140 nm wavelength.
Date: March 1, 1995
Creator: Griem, Hans R. & Elton, Raymond C.
Object Type: Report
System: The UNT Digital Library