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The Changing Use of Health Care Services by Unmarried Older Women, 1969 to 1975: Final Report to the NRTA-AARP Andrus Foundation

Description: Final report to the National Retired Teachers Association (NRTA)- American Association of Retired Persons (AARP) Andrus Foundation. This reports on a research study of the changing use of health care services by unmarried older women from 1969 to 1975.
Date: March 12, 1982
Creator: Martin, Cora A. & Eve, Susan Brown
Partner: UNT College of Public Affairs and Community Service

Human Rights and U.S. Foreign Policy

Description: Following a review of such broad policy issues, this report treats specific human rights issues of current interest. Discussions of controversy over the selection of an Assistant Secretary of State for Human Rights and Humanitarian Affairs and of human rights policy at the international financial institutions are followed by reviews of U.S. human rights policy toward Argentina, El Salvador, Nicaragua, South Africa, and the Soviet Union.
Date: November 24, 1982
Creator: Bite, Vita
Partner: UNT Libraries Government Documents Department

Health Maintenance Organizations

Description: This report discusses the "health maintenance organization", which is an entity that provides specific health services to its members for a prepaid, fixed payment.
Date: January 22, 1982
Creator: Price, Richard J
Partner: UNT Libraries Government Documents Department

Gun Control

Description: This report provides basic firearms-related issues and a summary of legislative action.
Date: August 11, 1982
Creator: Hogan, Harry L
Partner: UNT Libraries Government Documents Department

Geochemistry studies pertaining to the G-tunnel radionuclide migration field experiment

Description: This report presents the results of geochemical studies of Tunnel Bed tuff that were performed by Los Alamos National Laboratory or done at its direction as part of the Nevada Test Site G-Tunnel Radionuclide Migration Field Experiment. A tuff-treated water was prepared and used in laboratory-scale measurements of radionuclide sorption onto crushed Tunnel Bed tuff, pulverized fracture-fill material, tuff wafers, and a solid tuff core. Modelling studies were undertaken to determine the effects of matrix diffusion and unsaturated tuff on the proposed fracture-flow experiments. The initial results of those studies are presented in this report.
Date: November 1, 1982
Creator: Norris, A.E.; Aguilar, R.D. & Bayhurst, B.P.
Partner: UNT Libraries Government Documents Department

Monetary Policy: Recent Changes and Current Conditions

Description: This report summarizes the current status of monetary conditions and policy. The report also describes the process though which Congress oversees monetary policy, the recent changes in the financial system which affect monetary policy, and the October 1979 changes in Federal Reserve operating procedures.
Date: July 1, 1982
Creator: Driscoll, David D
Partner: UNT Libraries Government Documents Department

Effects of boundary conditions on thermomechanical calculations: Spent fuel test - climax

Description: The effects of varying certain boundary conditions on the results of finite-element calculations were studied in relation to the Spent Fuel Test - Climax. The study employed a thermomechanical model with the ADINA structural analysis. Nodal temperature histories were generated with the compatible ADINAT heat flow codes. The boundary conditions studied included: (1) The effect of boundary loading on three progressively larger meshes. (2) Plane strain vs plane stress conditions. (3) The effect of isothermal boundaries on a small mesh and on a significantly larger mesh. The results showed that different mesh sizes had an insignificant effect on isothermal boundaries up to 5 y, while on the smallest and largest mesh, the maximum temperature difference in the mesh was <1{sup 0}C. In the corresponding ADINA calculation, these different mesh sizes produce insignificant changes in the stress field and displacements in the region of interest near the heat sources and excavations. On the other hand, plane stress produces horizontal and vertical stress differences approx. 9% higher than does plane strain.
Date: October 1, 1982
Creator: Butkovich, T.R.
Partner: UNT Libraries Government Documents Department

Federal and State Authority to Regulate Radioactive Waste Disposal and Transportation

Description: There appears to be a growing controversy concerning whether a state has the authority to prevent the federal government from disposing of nuclear wastes within it and transporting nuclear wastes through it. Several states have statutes purporting to veto the federal government's action in these areas. This report investigates whether these state statutes may be unconstitutional and preempted by federal statutes and regulations.
Date: May 11, 1982
Creator: Seitzinger, Michael V
Partner: UNT Libraries Government Documents Department

Scoping analysis for radionuclide migration test

Description: The Lawrence Livermore National Laboratory is to conduct an in situ test of radionuclide migration in fractured granite. Radionuclides are to be injected into a fracture in the Climax Stock of the Nevada Test Site, then transported by fluid motion and subsequently withdrawn. The fluid will be injected through a borehole intersecting a near vertical fracture and withdrawn through a second borehole that intersects the fracture directly below the first. The scoping calculations presented here are intended to aid planning this experiment. In the absence of a detailed fracture description, this analysis treats the fracture as the space between parallel flat plates; the flow is a Hele-Shaw flow. The calculations predict the conditions for breakthrough of radionuclides at the outlet hole and describe the subsequent concentration history of fluid flowing from the fracture. The effects of advection, sorption, and geometric dispersion are treated.
Date: January 1, 1982
Creator: Morrison, F.A. Jr.
Partner: UNT Libraries Government Documents Department

Influence of heat flow on drift closure during Climax granite spent-fuel test: measurements and calculations

Description: Measurements of drift closure caused by the thermal load have been made routinely during the Spent Fuel Test in Climax granite since about six weeks after emplacement of the fuel. Horizontal and vertical closure was measured with a manually operated tape extensometer at various locations along the lengths of the drifts. Average closures ranged from 0 to 0.6 mm, horizontal and vertical, out to about 2.2 years since the start of the test. At the same time, displacements from the thermal loads were measured with rod extensometers emplaced to measure relative displacements between hole collars and anchor points in holes drilled from two parallel heater drifts. These data are compared with thermo-elastic finite element calculations which utilized measured properties of the Climax granite. The calculations show that more than half of the closures occur between fuel installation and the first closure measurement. The comparisons show that the results track each other, in that where closure followed by dilation is measured, the calculations also show this effect. The agreement is excellent, considering the averaged measured closures remain within 30% of the total calculated drift closures and the extremely small magnitude of the relative displacements (0.5 mm), measured or calculated.
Date: September 8, 1982
Creator: Butkovich, T.R.; Yow, J.L. Jr. & Montan, D.N.
Partner: UNT Libraries Government Documents Department

Spent-Fuel Test-Climax: a progress report

Description: Both operational and technical objectives are being pursued at the Spent-Fuel Test-Climax (SFT-C). The principal operational objective is to demonstrate the safe and reliable packaging, handling, and storage of spent nuclear reactor fuel in a deep geologic media and to retrieve the fuel afterward. Packaging of the spent fuel at the Engine Maintenance, Assembly and Disassembly (EMAD) facility, initial emplacement 420m below surface in the Climax granitic stock, and three subsequent exchanges of fuel canisters between EMAD and the SFT-C has demonstrated that application of straightforward engineering practices provides a safe and highly reliable system with no significant radiation exposure to the operating personnel. The primary technical objectives of the test are simulation of the thermal effects occurring in a panel of a large repository and comparison of the relative effects on the granitic host rock of heat alone versus heat in combination with ionizing radiation. Other technical objectives direct project activities toward instrument evaluation, ventilation effects, thermal and thermomechanical response of a jointed rock mass, and computer model validation. Recent findings from field measurements and laboratory studies are briefly discussed for: performance of data acquisition system and instrumentation; near-and intermediate-field temperature measurements; ventilation and dewpoint measurements; acoustic emission monitoring of fractures in granites; radiation-dose-to-granite measurements.
Date: September 20, 1982
Creator: Patrick, W.C. & Ballou, L.B.
Partner: UNT Libraries Government Documents Department

Spent Fuel Test-Climax: core logging for site investigation and instrumentation

Description: As an integral part of the Spent Fuel Test-Climax 5150 ft (1570 m) of granite core was obtained. This core was diamond drilled in various sizes, mainly 38-mm and 76-mm diameters. The core was teken with single tube core barrels and was unoriented. Techniques used to drill and log this core are discussed, as well as techniques to orient the core. Of the 5150 ft (1570 m) of core more than 3645 ft (1111 m) was retained and logged in some detail. As a result of the core logging, geologic discontinuities were identified, joint frequency and spacing characterized. Discontinuities identified included several joint sets, shear zones and faults. Correlations based on coring along were generally found to be impossible, even for the more prominent features. The only feature properly correlated from the exploratory drilling was the fault system at the end of the facility, but it was not identified from the exploratory core as a fault. Identification of discontinuities was later helped by underground mapping that identified several different joint sets with different characteristics. It was found that joint frequency varied from 0.3 to 1.1 joint per foot of core for open fractures and from 0.3 to 3.3/ft for closed or healed fractures. Histograms of fracture spacing indicate that there is likely a random distribution of spacing superimposed upon uniformly spaced fractures. It was found that a low angle joint set had a persistent mean orientation. These joints were healed and had pervasive wall rock alteration which made identification of joints in this set possible. The recognition of a joint set with known attitude allowed orientation of much of the core. This orientation technique was found to be effective. 10 references, 25 figures, 4 tables.
Date: May 28, 1982
Creator: Wilder, D.G.; Yow, J.L. Jr. & Thorpe, R.K.
Partner: UNT Libraries Government Documents Department

Spent fuel test. Climax data acquisition system integration report

Description: The Spent Fuel Test - Climax (SFT-C) is a test of the retrievable, deep geologic storage of commercially generated, spent nuclear reactor fuel in granitic rock. Eleven spent fuel assemblies, together with 6 electrical simulators and 20 guard heaters, are emplaced 420 m below the surface in the Climax granite at the Nevada Test Site. On June 2, 1978, Lawrence Livermore National Laboratory (LLNL) secured funding for the SFT-C, and completed spent fuel emplacement May 28, 1980. This multi-year duration test is located in a remote area and is unattended much of the time. An extensive array of radiological safety and geotechnical instrumentation is deployed to monitor the test performance. A dual minicomputer-based data acquisition system collects and processes data from more than 900 analog instruments. This report documents the design and functions of the hardware and software elements of the Data Acquisition System and describes the supporting facilities which include environmental enclosures, heating/air-conditioning/humidity systems, power distribution systems, fire suppression systems, remote terminal stations, telephone/modem communications, and workshop areas. 9 figures.
Date: June 1, 1982
Creator: Nyholm, R.A.; Brough, W.G. & Rector, N.L.
Partner: UNT Libraries Government Documents Department

Spent fuel test - Climax: technical measurements. Interim report, fiscal year 1981

Description: The Spent Fuel Test-Climax (SFT-C) is located 420 m below surface in the Climax granite stock on the Nevada Test Site. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized from April to May 1980, initiating the 3- to 5-year-duration test. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Technical objectives of the test led to development of a technical measurements program, which is the subject of this report. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 1-1/2 years of the test on more than 900 channels. Much of the acquired data are now available for analysis and are presented here. Highlights of activities this year include completion of site characterization field work, major modifications to the data acquisition and the management systems, and the addition of instrument evaluation as an explicit objective of the test.
Date: April 30, 1982
Creator: Patrick, W.C.; Ballou, L.B. & Butkovich, T.R.
Partner: UNT Libraries Government Documents Department

Characterization of Climax granite ground water

Description: The Climax ground water fails to match the commonly held views regarding the nature of deep granitic ground waters. It is neither dilute nor in equilibrium with the granite. Ground-water samples were taken for chemical analysis from five sites in the fractured Climax granite at the Nevada Test Site. The waters are high in total dissolved solids (1200 to 2160 mg/L) and rich in sodium (56 to 250 mg/L), calcium (114 to 283 mg/L) and sulfate (325 to 1060 mg/L). Two of the samples contained relatively high amounts of uranium (1.8 and 18.5 mg/L), whereas the other three contained uranium below the level of detection (< 0.1 mg/L). The pH is in the neutral range (7.3 to 8.2). The differences in composition between samples (as seen in the wide range of values for the major constituents and total dissolved solids) suggest the samples came from different, independent fracture systems. However, the apparent trend of increasing sodium with depth at the expense of calcium and magnesium suggests a common evolutionary chemical process, if not an interconnected system. The waters appear to be less oxidizing with depth (+ 410 mV at 420 m below the surface vs + 86 mV at 565 m). However, with Eh measurements on only two samples, this correlation is questionable. Isotopic analyses show that the waters are of meteoric origin and that the source of the sulfate is probably the pyrite in the fracture-fill material. Analysis of the measured water characteristics using the chemical equilibrium computer program EQ3 indicates that the waters are not in equilibrium with the local mineral assemblage. The solutions appear to be supersaturated with respect to the mineral calcite, quartz, kaolinite, muscovite, k-feldspar, and many others.
Date: August 1, 1982
Creator: Isherwood, D.; Harrar, J. & Raber, E.
Partner: UNT Libraries Government Documents Department

Comparison of measured and calculated radiation doses in granite around emplacement holes in the spent-fuel test: Climax, Nevada Test Site

Description: Lawrence Livermore National Laboratory (LLNL) has emplaced eleven spent nuclear-reactor fuel assemblies in the Climax granite at the Nevada Test Site as part of the DOE Nevada Nuclear-Waste Storage Investigations. One of our objectives is to study radiation effects on the rock. The neutron and gamma-ray doses to the rock have been determined by MORSE-L Monte Carlo calculations and measurements using optical absorption and thermoluminescence dosimeters and metal foils. We compare the results to date. Generally, good agreement is found in the spatial and time dependence of the doses, but some of the absolute dose results appear to differ by more than the expected uncertainties. Although the agreement is judged to be adequate for radiation effects studies, suggestions for improving the precision of the calculations and measurements are made.
Date: October 11, 1982
Creator: van Konynenburg, R. A.
Partner: UNT Libraries Government Documents Department

Laboratory studies of radionuclide transport in fractured Climax granite

Description: This report documents our laboratory studies of radionuclide transport in fractured granite cores. To simulate natural conditions, our laboratory studies used naturally fractured cores and natural ground water from the Climax Granite Stock at the Nevada Test Site. For comparison, additional tests used artificially fractured granite cores or distilled water. Relative to the flow of tritiated water, {sup 85}Sr and /sup 95m/Tc showed little or no retardation, whereas {sup 137}Cs was retarded. After the transport runs the cores retained varying amounts of the injected radionuclides along the fracture. Autoradiography revealed some correlation between sorption and the fracture fill material. Strontium and cesium retention increased when the change was made from natural ground water to distilled water. Artificial fractures retained less {sup 137}Cs than most natural fractures. Estimated fracture apertures from 18 to 60 {mu}m and hydraulic conductivities from 1.7 to 26 x 10{sup -3} m/s were calculated from the core measurements.
Date: June 1, 1982
Creator: Failor, R.; Isherwood, D.; Raber, E. & Vandergraaf, T.
Partner: UNT Libraries Government Documents Department

Instrumentation report 1: specification, design, calibration, and installation of instrumentation for an experimental, high-level, nuclear waste storage facility

Description: The Spent Fuel Test-Climax (SFT-C) is being conducted 420 m underground at the Nevada Test Site under the auspices of the US Department of Energy. The test facility houses 11 spent fuel assemblies from an operating commercial nuclear reactor and numerous other thermal sources used to simulate the near-field effects of a large repository. We developed a large-scale instrumentation plan to ensure that a sufficient quality and quantity of data were acquired during the three- to five-year test. These data help satisfy scientific, operational, and radiation safety objectives. Over 800 data channels are being scanned to measure temperature, electrical power, radiation, air flow, dew point, stress, displacement, and equipment operation status (on/off). This document details the criteria, design, specifications, installation, calibration, and current performance of the entire instrumentation package.
Date: January 1, 1982
Creator: Brough, W.G. & Patrick, W.C.
Partner: UNT Libraries Government Documents Department

Drilling-induced borehole-wall damage at spent fuel test-climax

Description: Microcracks in a sample of quartz monzonite from the Spent Fuel Test-Climax were measured by means of a scanning electron microscope in order to estimate the background level of damage near the borehole-wall. It appears that the hammer-drilling operation used to create the borehole has caused some microfracturing in a region 10 to 30 mm wide around the borehole. Beyond 30 mm, the level of microfracturing cannot be distinguished from background.
Date: December 1, 1982
Creator: Weed, H.C. & Durham, W.B.
Partner: UNT Libraries Government Documents Department

X-ray analysis of samples from LH84-2

Description: Each of these samples was analyzed using automated, scanning x-ray diffractometry. The blue vanadium surface was run in the as-received condition, while a new method of sample preparation was used for the scale. This new method involved (1) grinding the sample in a conventional fashion, (2) mixing the sample with collodion to form a castable slurry, (3) pouring and spreading the mixture on a taut, clean sheet of plastic film, and (4) then covering the resultant sample with a second plastic film layer to form a sandwich-type assembly. Only a few milligrams of sample are needed for this procedure, and the resultant data is much more accurate than that obtained by the previously-used Debye-Scherrer technique. The phase analysis for this sample finds vanadium as the major constituent and minor constituents of V{sub 2}C and a surface contaminant, PuO{sub 2}.
Date: August 4, 1982
Creator: Wallace, P.L. & Del Giudice, D.F.
Partner: UNT Libraries Government Documents Department

Engineering test plan for field radionuclide migration experiments in climax granite

Description: This Engineering Test Plan (ETP) describes field studies of radionuclide migration in fractured rock designed for the Climax grainite at the Nevada Test Site. The purpose of the ETP is to provide a detailed written document of the method of accomplishing these studies. The ETP contains the experimental test plans, an instrumentation plan, system schematics, a description of the test facility, and a brief outline of the laboratory support studies needed to understand the chemistry of the rock/water/radionuclide interactions. Results of our initial hydrologic investigations are presented along with pretest predictions based on the hydrologic test results.
Date: May 1, 1982
Creator: Isherwood, D.; Raber, E.; Stone, R.; Lord, D.; Rector, N. & Failor, R.
Partner: UNT Libraries Government Documents Department

Hydrologic test system for fracture flow studies in crystalline rock

Description: A hydrologic test system has been designed to measure the intrinsic permeabilities of individual fractures in crystalline rock. This system is used to conduct constant pressure-declining flow rate and pressure pulse hydraulic tests. The system is composed of four distinct units: (1) the Packer System, (2) Injection system, (3) Collection System, and (4) Electronic Data Acquisition System. The apparatus is built in modules so it can be easily transported and re-assembled. It is also designed to operate over a wide range of pressures (0 to 300 psig) and flow rates (0.2 to 1.0 gal/min). This system has proved extremely effective and versatile in its use at the Climax Facility, Nevada Test Site.
Date: May 5, 1982
Creator: Raber, E; Lord, D. & Burklund, P.
Partner: UNT Libraries Government Documents Department

Leasing of Energy and Mineral Resources on Federal Lands

Description: This report discusses the leasing of energy and mineral resources on federal lands. Leasing of energy minerals has been an issue of varying intensity for most of the past century, as oil, gas, and coal became indispensable commodities in both U.S. and world commerce.
Date: August 9, 1982
Creator: Lindahl, David M
Partner: UNT Libraries Government Documents Department

Summary report on the geochemistry of Yucca Mountain and environs

Description: This report gives a detailed description of work at Los Alamos that will help resolve geochemical issues pertinent to siting a high-level nuclear waste repository in tuff at Yucca Mountain, Nevada. It is necessary to understand the properties and setting of the host tuff because this rock provides the first natural barrier to migration of waste elements from a repository. The geochemistry of tuff is being investigated with particular emphasis on retardation processes. This report addresses the various aspects of sorption by tuff, physical and chemical makeup of tuff, diffusion processes, tuff/groundwater chemistry, waste element chemistry under expected repository conditions, transport processes involved in porous and fracture flow, and geochemical and transport modeling.
Date: December 1, 1982
Creator: Daniels, W.R.; Wolfsberg, K. & Rundberg, R.S.
Partner: UNT Libraries Government Documents Department