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Economic Study of the San Rafael River Desert Mining District Emery and Grand Counties, Utah

Description: Report documenting a geologic study of the San Rafael River Desert Mining District, including background describing the stratigraphy and geologic history, and the economic geology study containing more extensive descriptions of the area's mineralogy and uranium ores, including a description of mining and impacts.
Date: March 1957
Creator: Young, Robert G. (Robert Glen), 1923-2011; Million, I. & Hausen, Donald M.
Location: None
Partner: UNT Libraries Government Documents Department
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Geothermal R and D Project report for October 1, 1975--December 30, 1975

Description: The Idaho National Engineering Laboratory (INEL) Geothermal Research and Development Project is conducting two major geothermal development efforts: 1) a project aimed at medium temperature (approximately 300/sup 0/F) utilization to produce electricity with supplemental direct thermal use of the energy; and 2) a low temperature (approximately 170/sup 0/F) space heating project. The first effort has progressed in the field to the successful drilling of two deep geothermal wells providing flows of the desired temperature in the Raft River Valley of south central Idaho. The second program involves the heating of government buildings and a university campus at Boise, Idaho. This report covers the period October 1, to December 30, 1975.
Date: April 1, 1976
Partner: UNT Libraries Government Documents Department
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Application of pulsed electron beam vaporization to studies of UO/sub 2/. [LMFBR]

Description: A method for determining the pressure versus internal energy coordinates of the liquid-vapor saturation curve is applied to the study of UO/sub 2/. The experimental details and results of an initial series of tests are described. A comparison of the measurement results to models of the UO/sub 2/ equation of state illustrates the role of the heat capacity in describing the P--E characteristics of the state surface. A discussion of the available heat capacity information suggests that additional modeling and measurements of the heat capacity may be needed to give a complete temperature and energy dependent state surface description. Because of these modeling uncertainties, a method of thermodynamically describing the P(V, E) state surface entirely through the use of dynamic vapor measurements is given. Such a model satisfies transient thermomechanical analysis requirements. Next the effect of the state surface on one type of core disruptive reactor analysis is examined. And finally, the property determinations and models for UO/sub 2/ are reviewed with requirements for future work being outlined.
Date: June 1, 1977
Creator: Benson, D. A.
Partner: UNT Libraries Government Documents Department
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Global Warming: A Northwest Perspective

Description: The Northwest Power Planning Council convened a symposium in Olympia, Washington, on the subject of global climate change ( the greenhouse effect'') and its potential for affecting the Pacific Northwest. The symposium was organized in response to a need by the Power Council to understand global climate change and its potential impacts on resource planning and fish and wildlife planning for the region, as well as a need to understand national policy developing toward climate change and the Pacific Northwest's role in it. 40 figs., 15 tabs.
Date: February 1990
Creator: Scott, M. J. & Counts, C. A.
Partner: UNT Libraries Government Documents Department
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Phase 0: goal study for the technical and economic evaluation of the Compound Parabolic Concentrator (CPC) concept applied to solar thermal and photovoltaic collectors. Final report

Description: This report presents the results of a quick, six-week technical and economic evaluation of the compound parabolic concentrator (CPC) solar collector. The purpose of this effort was to provide an initial phase of a goals study that is directed toward recommending relative priorities for development of the compound parabolic concentrator concept. The findings of this study are of a very preliminary nature. Conclusions based on study findings at this depth should be considered preliminary and subject to revision and review in later phases.
Date: June 1, 1975
Partner: UNT Libraries Government Documents Department
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Sensitivity of the reactor safety study consequences model to mixing heights

Description: The sensitivity to mixing height values of the consequence model used in the Reactor Safety Study has been investigated. Increasing mixing height values by a factor of 2 or decreasing by factors of 2, 5, or 10 had negligible effects on early-fatality predictions. Plume penetration of a low-lying inversion layer substantially decreases early-fatality predictions. Therefore, consequence model predictions are insensitive to mixing height values and conservative with respect to plume penetration of inversion layers, a process not currently included in the model.
Date: January 1, 1977
Creator: Sprung, J. L. & Church, H. W.
Partner: UNT Libraries Government Documents Department
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Dynamic Isotope Power System: technology verification phase, program plan, 1 October 1978

Description: The technology verification phase program plan of the Dynamic Isotope Power System (DIPS) project is presented. DIPS is a project to develop a 0.5 to 2.0 kW power system for spacecraft using an isotope heat source and a closed-cycle Rankine power-system with an organic working fluid. The technology verification phase's purposes are to increase the system efficiency to over 18%, to demonstrate system reliability, and to provide an estimate for flight test scheduling. Progress toward these goals is reported. (LCL)
Date: January 15, 1979
Partner: UNT Libraries Government Documents Department
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DENSJT: statistical shell-model level density computer code description and user's manual. [In FORTRAN for CDC Cyber-70 computer]

Description: The FORTRAN code DENSJT described here is constructed to calculate the appropriate moments and dimensions needed in describing the Gaussian level density for fixed values of the total angular momentum (J) and isobaric spin (T = T/sub 0/). The input for this code is the same as in the usual shell-model codes, namely, the single-particle orbital properties and the antisymmetric two-body matrix elements. To calculate the moments for fixed values of the angular momentum (J) a method described by Ginocchio is used. All of the ''basic inputs'' needed in the reduction formula were derived without any restrictions on the orbitals. The formulas used in DENSJT are described, and the basic inputs are listed in tables. A block flow chart showing the general structure and the specific function of each subroutine is included. All necessary information for the input and output of this code is described. A calculation involving 3 orbitals in the s--d shell took 1 second on a CDC Cyber-70 computer. (RWR)
Date: July 1, 1976
Creator: Dalton, B.
Partner: UNT Libraries Government Documents Department
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Photoelectron spectroscopy and Auger electron spectroscopy of solids and surfaces

Description: The use of photoelectron spectroscopy, primarily x-ray photoelectron spectroscopy, to obtain information on the electronic structure of a wide variety of solids (especially the bulk electronic structure of solids) is covered. Both valence band and core-level spectra, as well as a few cases of photon excited Auger electron spectroscopy, are employed in the investigations to derive information on N(E). The effect of several modulations inherent in the measured I(E)'s, such as final state band structure, cross section, and relaxation, is discussed. Examples of many-electron interactions in PES are given. Some experimental aspects of PES and AES studies are given with emphasis on sample preparation techniques. Multiple splitting of core levels is examined using the Mn levels in MnF/sub 2/ as a detailed case study. Core level splittings in transition metals, rare earth metals, transition metal halides and several alloys are also reported. The application of PES to the study of the chemical bond in some crystalline semiconductors and insulators, A/sup N/B/sup 8-N/ and A/sup N/B/sup 10-N/ compounds is treated, and a spectroscopic scale of ionicity for these compounds is developed from the measured ''s-band'' splitting in the valence band density of states. (GHT)
Date: January 1, 1976
Creator: Kowalczyk, S. P.
Partner: UNT Libraries Government Documents Department
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Effects of impurities on PuO/sub 2/ dissolution in nitric-hydrofluoric acid solutions

Description: The effects of 0.10 M Cu/sup 2 +/, Hg/sup 2 +/, Zn/sup 2 +/, La/sup 3 +/, Ce/sup 3 +/, Al/sup 3 +/, Th/sup 4 +/,Zr/sup 4 +/, Cr/sup 3 +/, and Fe/sup 3 +/ on PuO/sub 2/ dissolution in 8.0M HNO/sub 3/--0.1M HF were investigated. Except for Cr/sup 3 +/ and Fe/sup 3 +/, the amount of Pu dissolved in 1 hour can be predicted by either log C(Pu) = -0.32 log K/sub F/ - 1.53 (K/sub F/ = first stability constant for the impurity metal fluoride complex) or log C(Pu) = -0.5 Z/sup 2//d-1.11 (Z = ionic charge of impurity cation, d = sum of impurity cation and fluoride ionic radii in angstroms) (DLC)
Date: January 1, 1976
Creator: Tallent, O. K. & Mailen, J. C.
Partner: UNT Libraries Government Documents Department
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Nuclear Chemistry Research. Annual progress report, 1 January--31 December 1975. [Summaries of research activities at Pittsburgh University]

Description: Research is summarized on heavy ion fusion reactions, equilibrium charge-state distributions of heavy ions, the statistics of low level counting, and strontium and radiostrontium in marine mollusc shells. A list of publications is included. (JFP)
Date: January 1, 1976
Creator: Wolke, R L
Partner: UNT Libraries Government Documents Department
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Telemetry component tests in the FN tandem terminal

Description: When an electrostatic tandem accelerator is used primarily for heavy ion acceleration, numerous communication channels with the high voltage terminal are desirable. The ANL FN tandem operates at a tank pressure of 100 psi SF/sub 6/ at terminal voltages up to 9.5 MeV. A low powered He-Ne laser with 15 percent modulation has been successfully tested in the terminal under normal operating conditions. Such a system allows the transmission of information without the use of light guides. Multistranded light guides did not withstand voltage gradients as low as 0.4 MV/m. Single core light guides with a diameter of 0.5 mm have been successfully operated at voltage gradients in excess of 1.7 MV/m. In addition to the laser a microprocessor has also been tested in the tandem terminal. With suitable protection, an 8080 microprocessor and a programmable ROM operated successfully for several weeks under normal operating conditions.
Date: January 1, 1977
Creator: Bicek, J. J.; Billquis, P. J. & Yntema, J. L.
Partner: UNT Libraries Government Documents Department
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Geothermal resources: exploration and exploitation. A bibliography

Description: This comprehensive bibliography contains 5476 citations of foreign and domestic research reports, journal articles, patents, conference proceedings, and books concerned with the exploration and exploitation of geothermal resources. The coverage dates back as far as useful references could be obtained and extends through June 1976. References are arranged in broad subject categories and are made up of complete bibliographic citations. These are followed by a listing of subject descriptors used to describe the subject content of each reference. Four indexes are included: Corporate, Personal Author, Subject, and Report Number. Also included is a list of journals from which articles were selected. (LBS)
Date: July 1, 1976
Partner: UNT Libraries Government Documents Department
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Formation and study of exciplex systems: a low-pressure approach. Quarterly progress report No. 2, March 1, 1976--May 31, 1976

Description: A system is being developed for forming and studying excimers from the van der Waals ground states of gases. Status of the apparatus is reported. Calculations were made for concentration of dimers in cluster beams of noble gas mixtures. An experiment using a tuned laser to study the resonant absorption of excimers is proposed. (DLC)
Date: January 1, 1976
Creator: Sanzone, G.
Partner: UNT Libraries Government Documents Department
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Advanced NMR-based techniques for pore structure analysis of coal

Description: One of the main problems in coal utilization is the inability to properly characterize its complex pore structure. Coals typically have micro/ultra-micro pores but they also exhibit meso and macroporosity. We believe that measurement of the NMR parameters of various gas phase and adsorbed phase NMR active probes can provide the resolution to this problem. We will investigate the dependence of the common NMR parameters such as chemical shifts and relaxation times of several different nuclei and compounds on the pore structure of model microporous solids, carbons, and coals. In particular, we will study the interaction between several small molecules ({sup 129}Xe, {sup 3}He, {sup 2}H{sub 2}, {sup 14}N{sub 2}, {sup 14}NH{sub 3}, {sup 15}N{sub 2}, {sup 13}CH{sub 4}, {sup 13}CO{sub 2}) and the pore surfaces in coals. These molecules have been selected for their chemical and physical properties. A special NMR probe will be constructed which will allow the concurrent measurement of NMR properties and adsorption uptake at a variety of temperatures. All samples will be subjected to a suite of conventional'' pore structure analyses. These include nitrogen adsorption at 77 K with BET analysis, C0{sub 2} and CH{sub 4} adsorption at 273 K with D-R (Dubinin-Radushkevich) analysis, helium pycnometry, and small angle X-ray scattering as well as gas diffusion measurements. The project combines expertise at the UNM (pore structure, NMR), Los Alamos National Laboratory (NMR), and Air Products (porous materials).
Date: January 1, 1992
Creator: Smith, D. M.
Partner: UNT Libraries Government Documents Department
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OSCIL: one-dimensional spring-mass system simulator for seismic analysis of high temperature gas cooled reactor core

Description: OSCIL is a program to predict the effects of seismic input on a HTGR core. The present model is a one-dimensional array of blocks with appropriate spring constants, inter-elemental and ground damping, and clearances. It can be used more generally for systems of moving masses separated by nonlinear springs and dampers.
Date: January 1, 1976
Creator: Lasker, L. (ed.)
Partner: UNT Libraries Government Documents Department
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Silica scale technology and water conservation. [Recirculating evaporative cooling]

Description: Conservation of water at the Los Alamos Scientific Laboratory (LASL) has been accomplished by recirculating evaporative cooling waters. Because of high silica concentration (80 mg/l) in Los Alamos groundwater, the concentration of recirculating water must be carefully controlled to prevent scaling. The most troublesome scale at Los Alamos has been identified as colloidal silica bound in a crystalline matrix of calcium carbonate. Several approaches to controlling this scale are: (1) chemical treatment using a chelate, sequestrant, or threshold approach, (2) softening, or (3) pH control. Silica alone will form deposits when supersaturated. In LASL systems, where silica concentrations are 200 to 240 mg/l, no problems have been observed. However, there is evidence that deposits are forming at slightly higher concentrations. These amorphous silica deposits are not as hard and tenacious as the calcium carbonate--silica scale. Complete external treatment, which combines silica removal and water softening, may be an economically competitive process for scale control. The advantages of slightly reducing the quantity of makeup water and drastically reducing the amount of blowdown water have environmental and conservation implications that may encourage the selection of complete treatment.
Date: January 1, 1976
Creator: Midkiff, William S. & Foyt, H. Pressley
Partner: UNT Libraries Government Documents Department
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Enhancement of DIII-D neutral beam system for higher performance

Description: The DIII-D tokamak employs eight neutral beam systems for plasma heating and current drive experiments. These positive ion source neutral beam systems have gone through several improvements in operational technique and in system hardware since the start of conditioning of the first long pulse ion source in December 1986. These improvements have led to the routine operation in deuterium at beam power levels of 20 MW. The improvements in operational technique include filament power supply operating mode, accelerator grid voltage holding capability, mid changes in grid potential gradients. The hardware improvements include installation of arc notching, arc discharge density regulation, and control of neutralizer gas puffing. Each of these improvements are discussed in this paper. Successful testing and operation of the ion source at 93 kV deuterium beam energy, well above the design value of 80 kV, also led to the possibility of enhancing system capability to 28 MW power level, nearly twice the original design value. Upgrading of the beam system to 60 second pulse duration at the currently achieved power level is under consideration. Studies have shown that this pulse length extension can be achieved with improvements in beamline heat handling components and auxiliary systems, especially the power supply system. The drift duct (the section between neutral beam beamline and tokamak) upgrade and protection for the long pulse duration present the greatest challenges, and are crucial to achieving long pulse beam injection into the tokamak plasma.
Date: September 1, 1992
Creator: Hong, R.; Colleraine, A. P.; Kellman, D. H.; Kim, J.; Luxon, J. L.; Nerem, A. et al.
Partner: UNT Libraries Government Documents Department
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Review of the US Department of Energy Classified Visits Program

Description: This review examines the US Department of Energy (DOE) Classified Visits Program, which is administered by the Office of Safeguards and Security. The overall purpose of this analysis is to (1) ensure that DOE policy and implementing procedures are appropriate to maintain US national security intentions; (2) evaluate the effectiveness of the process used across the DOE complex; and (3) recommend changes which will enhance the overall efficiency of the process while maintaining the program's integrity.
Date: July 1, 1992
Creator: Martin, S. W.; Killinger, M. H. & Segura, M. A.
Partner: UNT Libraries Government Documents Department
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Run - Beyond - Cladding - Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program

Description: In 1984 Argonne National Laboratory (ANL) began an aggressive program of research and development based on the concept of a closed system for fast-reactor power generation and on-site fuel reprocessing, exclusively designed around the use of metallic fuel. This is the Integral Fast Reactor (IFR). Although the Experimental Breeder Reactor-II (EBR-II) has used metallic fuel since its creation 25 yeas ago, in 1985 ANL began a study of the characteristics and behavior of an advanced-design metallic fuel based on uranium-zirconium (U-Zr) and uranium-plutonium-zirconium (U-Pu-Zr) alloys. During the past five years several areas were addressed concerning the performance of this fuel system. In all instances of testing the metallic fuel has demonstrated its ability to perform reliably to high burnups under varying design conditions. This paper will present one area of testing which concerns the fuel system's performance under breach conditions. It is the purpose of this paper to document the observed post-breach behavior of this advanced-design metallic fuel. 2 figs., 1 tab.
Date: January 1, 1990
Creator: Batte, G. L. (Argonne National Lab., Idaho Falls, ID (USA)) & Hoffman, G. L. (Argonne National Lab., IL (USA))
Partner: UNT Libraries Government Documents Department
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Using the Tritium Plasma Experiment to evaluate ITER PFC safety. [Plasma-Facing Components]

Description: The Tritium Plasma Experiment was assembled at Sandia National Laboratories, Livermore to investigate interactions between dense plasmas at low energies and plasma-facing component materials. This apparatus has the unique capability of replicating plasma conditions in a tokamak divertor with particle flux densities of 2 [times] 10[sup 19] ions/cm[sup 2] [center dot] s and a plasma temperature of about 15 eV using a plasma that includes tritium. With the closure of the Tritium Research Laboratory at Livermore, the experiment was moved to the Tritium Systems Test Assembly facility at Los Alamos National Laboratory. An experimental program has been initiated there using the Tritium Plasma Experiment to examine safety issues related to tritium in plasma-facing components, particularly the ITER divertor. Those issues include tritium retention and release characteristics, tritium permeation rates and transient times to coolant streams, surface modification and erosion by the plasma, the effects of thermal loads and cycling, and particulate production. A considerable lack of data exists in these areas for many of the materials, especially beryllium, being considered for use in ITER. Not only will basic material behavior with respect to safety issues in the divertor environment be examined, but innovative techniques for optimizing performance with respect to tritium safety by material modification and process control will be investigated. Supplementary experiments will be carried out at the Idaho National Engineering Laboratory and Sandia National Laboratory to expand and clarify results obtained on the Tritium Plasma Experiment.
Date: January 1, 1993
Creator: Longhurst, G. R.; Anderl, R. A. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Bartlit, J. R. (Los Alamos National Lab., NM (United States)); Causey, R. A. (Sandia National Labs., Livermore, CA (United States)) & Haines, J. R. (MDC Aerospace, St. Louis, MO (United States))
Partner: UNT Libraries Government Documents Department
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Engineering, maintenance, and new initiatives to improve LAMPF beam availability and system reliability

Description: Two different requirements are driving engineering studies and hardware development to improve LAMPF. The first is concerned with component and system improvements to increase beam availability during the LAMPF production cycle. Hardware changes in RF, power supplies, and magnets are being implemented to increase mean time between failure and reduce time to replace or repair failed units. A joint LAMPF-Industry project is on-going to improve reliability of RF components. A component test stand is being refurbished to include significant development capability. The second approach includes several changes that will increase the duty factor of the existing accelerator. Major changes are being evaluated for replacing the front end of the accelerator. Other changes improving high brightness capability could result in a new performance plateau for LAMPF.
Date: January 1, 1992
Creator: Harris, H. W.; DeHaven, R. A.; Hart, V. E.; Parsons, W. M. & Sturrock, J. C.
Partner: UNT Libraries Government Documents Department
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Investigations of the inductively coupled plasma source for analyzing NURE water samples at the Los Alamos Scientific Laboratory

Description: A 3.4-meter direct-reading spectrograph is being used with an inductively coupled plasma source for the simultaneous determination of Ag, Bi, Cd, Cu, Nb, Ni, Pb, Sn, and W in water samples. We have attached a small digital computer to the system in order to obtain intensity data on each element once a second. After the intensities during a run on a sample have stabilized, the computer records the intensity data and outputs the average concentration for each element. To approach the published detection limits, a peristaltic pump must be used to force the water sample into the usual cross-flow nebulizer. We have studied several different nebulizer designs with the goal of improving efficiency and hence sensitivity. One design, the fritted-disk nebulizer, has an efficiency over 60 percent, as compared with the 5 percent efficiency of the original nebulizer.
Date: March 1, 1977
Creator: Apel, C. T.; Bieniewski, T. M.; Cox, L. E. & Steinhaus, D. W.
Partner: UNT Libraries Government Documents Department
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Storage of LWR (light-water-reactor) spent fuel in air

Description: An experimental program is being conducted at Pacific Northwest Laboratory (PNL) to determine the oxidation response of light-water-reactor (LWR) spent fuels under conditions appropriate to fuel storage in air. The program is designed to investigate several independent variables that might affect the oxidation behavior of spent fuel. Included are temperature (135 to 230{degree}C), fuel burnup (to about 34 MWd/kgM), reactor type (pressurized and boiling water reactors), moisture level in the air, and the presence of a high gamma field. In continuing tests with declad spent fuel and nonirradiated UO{sub 2} specimens, oxidation rates were monitored by weight-gain measurements and the microstructures of subsamples taken during the weighing intervals were characterized by several analytical methods. The oxidation behavior indicated by weight gain and time to form powder will be reported in Volume III of this series. The characterization results obtained from x-ray diffractometry, transmission electron microscopy, scanning electron microscopy, and Auger electron spectrometry of oxidized fuel samples are presented in this report. 28 refs., 21 figs., 3 tabs.
Date: December 1, 1989
Creator: Thomas, L. E.; Charlot, L. A.; Coleman, J. E. (Pacific Northwest Lab., Richland, WA (USA)) & Knoll, R. W. (Johnson Controls, Inc., Madison, WI (USA))
Partner: UNT Libraries Government Documents Department
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