15,051 Matching Results

Search Results

Guide for commercialization of energy-related new products or processes. Final report. [Handbook]

Description: This guide was prepared for small technical companies and inventor-entrepreneurs for the commercialization of energy-related new products or processes. Tasks I, II, III, IV, and VII are included in this Final Report. Tasks V, VI, VIII, IX, and X are concerned directly with the preparation of the book and are contained in the manuscript which has already been submitted to the Inventions Program Office. The tasks included are: Functional Analysis of the Commercialization Process; Analysis of ERDA/AASRC (American Association of Small Research Companies) Seminars; Identify Barriers to SBI Participation; Identify SBI Marketing Needs; and Cost Benefit Analysis of Publishing Options. (MCW)
Date: January 1, 1979
Creator: ,
Partner: UNT Libraries Government Documents Department

Structure and chemistry of coals: calorimetric analyses. [Wetting heat]

Description: Heats of immersion (h/sub i/) of coals have been shown to be a valuable means of investigating structure and chemistry of coals. This report outlines some of the factors involved. Lower ranked coals imbibe more liquids (i.e., H/sub 2/O) onto more polar sites (carbonyl, phenolic, etc.) than higher ranked coals. Mineral matter reacts strongly with polar liquids (i.e., H/sub 2/O) giving rise to enhanced h/sub i/. Grinding of coals not only decreases particle size but modifies the coal structure to an increasing degree dependent upon the extent and severity of grinding. The magnitude of h/sub i/ and the rate of reaction are both modified consistent with the existence of a shrinking core or unperturbed coal structure serving as substrate to which the modified (less ordered) material is bound. Chemical (alkali) attack seems to loosen the coal structure markedly to allow enhanced access to fluid reagents. These exploratory studies have shown that calorimetric analyses similar to those developed and used by A.C. Zettlemoyer and his coworkers are excellent means for elucidating the structure and chemistry of coals and related materials.
Date: January 1, 1979
Creator: ,
Partner: UNT Libraries Government Documents Department

Hydrogeochemical and stream sediment reconnaissance of the National Uranium Resource Evaluation Program primarily for the Rocky Mountain states of New Mexico, Colorado, Wyoming, and Montana, and the State of Alaska. Semiannual progress report, October 1978-March 1979

Description: During this six-month period, Hydrogeochemical and Stream Sediment Reconnaissance samples were collected by the Los Alamos Scientific Laboratory (LASL) from 623 locations in Colorado for a special study. Additional special studies are planned for nine other areas in the Rocky Mountain states in fiscal year 1979, plus some cleanup reconnaissance sampling in parts of four quadrangles that overlap state borders. Preparations for reconnaissance sampling of the entire North Slope region of Alaska have been made but sampling is contingent upon receiving supplemental funds. Water samples from 6725 locations were analyzed for uranium by fluorometry or delayed-neutron counting (DNC). Water samples from 9390 locations were analyzed by emission spectroscopy for 12 other elements. Sediment samples from 14,414 locations were analyzed for uranium and 31 other elements by combined DNC and neutron activation analysis. Sediment samples from 9876 locations were analyzed for two additional elements by x-ray fluorescence. Nine LASL reconnaissance reports, one pilot study data release, one supplemental multielement data release, a multielement data release for three areas in western Alaska, and one quarterly report were open filed by the Department of Energy, Grand Junction Office during the six-month period. Numerous other reports are in various stages of completion and several will be open filed in the near future.
Date: July 1, 1979
Creator: Aamodt, P.L.; Bunker, M.E.; Waterbury, G.R. & Waller, R.A.
Partner: UNT Libraries Government Documents Department

Uranium Hydrogeochemical and Stream Sediment Reconnaissance of the McGrath and Talkeetna NTMS Quadrangles, Alaska, Including Concentrations of Forty-Three Additional Elements

Description: From abstract: During the summer of 1977, 1268 water and 1206 sediment samples were collected from 1292 lakes and streams throughout the 33 600-km2 area within the boundaries of the McGrath and Talkeetna National Topographic Map Series quadrangles in south-central Alaska. Each of the water samples was analyzed for uranium and 12 other elements, and each of the sediment samples was analyzed for uranium, thorium, and 41 other elements. All of the field and analytical data are listed in appendixes to this report, but only the uranium and thorium data are discussed herein.
Date: April 1979
Creator: Aamodt, Paul L.; Jacobsen, Sue Israel & Hill, Dwight E.
Partner: UNT Libraries Government Documents Department

Development of cermets for high level radioactive waste fixation

Description: A method for the solidification and fixation of commercial and defense high-level radioactive wastes, namely a cermet process, is currently under development. Chemical and physical processing techniques, as developed up to this time, and the subsequent properties of the resulting cermet bodies are described; unique and advantageous features of the cermet waste form and the conversion process are discussed.
Date: January 1, 1979
Creator: Aaron, W S; Quinby, T C & Kobisk, E H
Partner: UNT Libraries Government Documents Department

Development and characterization of cermet forms for radioactive waste

Description: Cermets designed to isolate high-level wastes in a solid form are a composite consisting of various ceramic phase particles uniformly dispersed in and microencapsulated by an iron-nickel base alloy matrix. The metal matrix provides this waste form with many advantageous features including excellent thermal conductivity and mechanical strength. These cermets are formed by first dissolving the waste in molten urea, precipitating and calcining all the constituents, compacting the calcine, and sintering and reduction to form the final product. The exact formulation of cermets through additions to the waste is designed to fix most of the fission products in stable, leach resistant ceramic phases which are subsequently microencapsulated by an alloy matrix. The alloy matrix, which is derived primarily from the waste itself and includes the reducible fission and activation products from the waste, can be compositionally adjusted through additions to optimize its corrosion resistance under conditions existing in various disposal environments. The processes by which cermets are formed include several new and unique materials preparation options that are being developed to permit engineering scale-up and to be compatible with remote operations. Cermets formed by alternate processing methods are being characterized. Initially, cermet samples were prepared using a laboratory scale, batch process developed for the preparation of special ceramics having high compositional uniformity and excellent sinterability. The modification of this batch process to one suitable for scale-up and remote operation is the subject of this paper. Cermet characterization is also discussed.
Date: January 1, 1979
Creator: Aaron, W.S.; Quinby, T.C. & Kobisk, E.H.
Partner: UNT Libraries Government Documents Department

Soviet Oil Politics and the Middle East

Description: This investigation, covering the past two decades, attempts to determine what benefits the Soviets have sought to gain in their relationships with Middle Eastern oil-producing nations. Chapter I surveys the U.S.S.R.'s oil industry and its tentative prospects for the 1980's. Chapter II discusses Soviet involvement in the Middle East since 1950, including nationalization and oil embargoes. In Chapter III, developments less favorable to the U.S.S.R. are, analyzed: the growing influence of conservative, anti -Soviet oil-producing states and the deradicalization of other Middle Eastern nations. Chapter IV concludes that the Soviets have met with varying success in their Middle Eastern involvements. The future of their oil industry remains uncertain.
Date: December 1979
Creator: Abbas, Ehsan A. R.
Partner: UNT Libraries

Water use alternatives for Navajo energy production

Description: The Navajo have substantial resources of coal and uranium, and water use is certain to accompany development of these resources. A variety of supplies, however, are available--water in storage in Navajo Reservoir, water in existing uses which may be transferred, and groundwater. Furthermore, the quantity of water use varies over a wide range depending on the use of water conservation technologies such as dry coolers and wastewater treatment units. Joint management of energy and water resources requires a basic understanding of the water supply and demand alternatives available to the energy industry. Thus, the uses of water for key energy activities--coal and uranium mining, coal transportation (slurry pipelines), and coal conversion (electricity and synthetic gas production) are reviewed. For those activities for which water conservation is feasible, the technologies and estimate costs ($/af saved) are described. The range of water requirements are then compared to energy and water resource estimates. Finally, alternative (not necessarily exclusive) criteria for energy and water resource management are discussed: a) promote energy activities with the lowest minimum water requirements; b) require industry to use low-quality water resources and the most effective water conservation technology; and c) maximize the economic return on Navajo water resources ($/af consumed).
Date: January 1, 1979
Creator: Abbey, D.
Partner: UNT Libraries Government Documents Department

Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics

Description: A fuel cycle that employs /sup 233/U denatured with /sup 238/U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured /sup 233/U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed. The scope of the R, D and D programs to commercialize these reactors and their associated fuel cycles is also summarized and the resource requirements and economics of denatured /sup 233/U cycles are compared to those of the conventional Pu/U cycle. In addition, several nuclear power systems that employ denatured /sup 233/U fuel and are based on the energy center concept are evaluated.
Date: December 1, 1979
Creator: Abbott, L.S.; Bartine, D.E. & Burns, T.J. (eds.)
Partner: UNT Libraries Government Documents Department

Large aperture contact ionized Cs/sup +1/ ion source for an induction linac

Description: A 500 KeV one-ampere Cs/sup +1/ ion beam has been generated by contact ionization with a 30 cm dia. iridium hot plate. Reproducibility of space charge limited ion current wave forms at repetition rates up to 1 Hz has been verified. The beam is characterized to be very bright and suitable as an ion source for the induction linac based heavy ion fusion scheme. The hot anode plate was found to be reliable and self-cleaning during the operation.
Date: March 1979
Creator: Abbott, Steven; Chupp, Warren; Faltens, Andris; Herrmannsfeldt, William; Hoyer, Egon; Keefe, Denis et al.
Partner: UNT Libraries Government Documents Department

QIKMIX: a quick-turnaround computer program for computing opacities of mixtures

Description: QIKMIX is a quick-turnaround computer code developed to compute the radiative Rosseland mean opacity of specified mixtures at specified temperature and density points. The QIKLIB data base, which QIKMIX uses, has been derived from the OPLIB library. For most mixtures, QIKMIX can compute opacities over a temperature range of 50 to 25,000 eV in less than 1 min of CDC 7600 computer time. The purpose of this report is to discuss the QIKLIB data base and the operation of the QIKMIX code.
Date: May 1, 1979
Creator: Abdallah, J. Jr. & Huebner, W.F.
Partner: UNT Libraries Government Documents Department

Growth of molten core debris pools in concrete. Part II. A. Pool growth in composite beds; B. Effect of overlaying steel layers. Final report, March 1, 1978-September 30, 1979. [LMFBR]

Description: The heat and mass transfer processes taking place in molten core debris/concrete systems have been experimentally investigated. Two types of experiments have been conducted. The first experiment simulates the growth of a molten debris pool in a composite sacrificial bed. This experiment models debris pool growth in an inner, low-melting point, sacrificial material zone followed by a melting attack on the concrete bed. The purpose of the inner zone is to quickly melt and dilute the debris pool so that its subsequent downward growth in the concrete may be slowed. In the second experiment a two-layer immiscible liquid system is volumetrically heated and allowed to melt into a low-density gas releasing solid bed which is miscible in the initially-higher-density bottom liquid. The solid melts, mixes with, and dilutes the bottom liquid pool until its density is lower than that of the top liquid.
Date: December 26, 1979
Creator: Abdel-Khalik, S I
Partner: UNT Libraries Government Documents Department

Growth of molten core debris pools in concrete. Progress report, April 1--June 30, 1979. [LMFBR]

Description: The heat and mass transfer processes taking place in molten core debris/concrete systems have been experimentally investigated. Two types of experiments have been conducted. The first experiment simulates the growth of a molten debris pool in a composite sacrificial bed. This experiment models debris pool growth in an inner, low-melting point, sacrificial material zone followed by a melting attack on the concrete bed. The purpose of the inner zone is to quickly melt and dilute the debris pool so that its subsequent downward growth in the concrete may be slowed. In the second experiment a two-layer immiscible liquid system is volumetrically heated and allowed to melt into a low-density gas-releasing solid bed which is miscible in the initially-higher-density bottom liquid. The solid melts, mixes with, and dilutes the bottom liquid pool until its density is lower than that of the top liquid. At this time pool inversion occurs and the immiscible liquid sinks to the bottom of the pool displacing the now lighter fuel-concrete simulant.
Date: July 1, 1979
Creator: Abdel-Khalik, S I
Partner: UNT Libraries Government Documents Department

Results of systems studies for the STARFIRE commercial tokamak

Description: Extensive system and tradeoff studies were performed to support the selection process for the major parameters and design features of the STARFIRE commercial reactor. With a thermal power of 3800 MW, a neutron wall load of 3.5 MW/m/sup 2/ results in a relatively small-size reactor without imposing excessive requirements on the first-wall cooling capability, maximum toroidal-magnetic field, and frequency of structural material requirements. This moderately high-wall load requires that the first-wall coolant be liquid (water or lithium) and the lifetime of the structural material is > 15 MW-y/m/sup 2/. With moderate plasma elongation and beta the required maximum toroidal-field is approx. 11 T. STARFIRE is operated steady-state with no OH coil. The absence of an OH coil makes it possible to design the reactor with a low-aspect ratio (approx. 2.5) and small major radius. However, higher aspect ratios (approx. 3.5-4) are favored when the plasma current is driven with rf because the power required for the current drive, P/sub rf/, is much larger at lower aspect ratio. Since P/sub rf/ increases at lower plasma temperature, the optimum design for STARFIRE requires operation with plasma temperatures higher than those normally selected for designs with OH-driven current.
Date: January 1, 1979
Creator: Abdou, M.A.; Ehst, D.A. & Waganer, L.M.
Partner: UNT Libraries Government Documents Department

Shielding and maintainability in an experimental tokamak

Description: This paper presents the results of an attempt to develop an understanding of the various factors involved. This work was performed as a part of the task assigned to one of the expert groups on the International Tokamak Reactor (INTOR). However, the results of this investigation are believed to be generally applicable to the broad class of the next generation of experimental tokamak facilities such as ETF. The shielding penalties for requiring personnel access are quantified. This is followed by a quantitative estimate of the benefits associated with personnel access. The penalties are compared to the benefits and conclusions and recommendations are developed on resolving the issue.
Date: January 1, 1979
Creator: Abdou, M.A.; Fuller, G.; Hager, E.R. & Vogelsang, W.F.
Partner: UNT Libraries Government Documents Department

Influence of access hole parameters on neutron moisture probe readings

Description: Computing soil moisture content with a neutron probe requires use of a calibration curve that considers the thermal neutron capture cross section of the hole liner, as well as the hole diameter. The influence of steel, polyvinyl chloride, and aluminum casings that fit 0.051- to 0.102-m hole diameters was determined by comparison with neutron probe readings in uncased holes of corresponding diameters. Eccentricity of probe location was considered a potentially significant variable. The experiment was run in disturbed Bandelier tuff with an average dry density of 1.35g . cm/sup -3/ and moisture content of 3.8 to 26.7% by volume. The casing material and hole diameter influenced the probe readings significantly, whereas eccentric location of the probe did not. Regression analyses showed an almost perfect inverse linear correlation between hole diameter and count rate.
Date: October 1, 1979
Creator: Abeele, W.V.
Partner: UNT Libraries Government Documents Department

Use of a General Nonlinear Least-Squares Curve Fitting Program with nonclosed form relationships. [GNLS, in FORTRAN for CDC computers]

Description: A use for GNLS, a general nonlinear least-squares curve fitting program, is presented. In this use GNLS determines a set of best parameters for relationships that cannot be written in closed form. This program can be useful for experimenters who need to determine experimental parameters by fitting nonclosed-form relationships to experimental data. Two examples are given to indicate how GNLS can be used for this type of problem. 11 figures.
Date: December 26, 1979
Creator: Abey, A.E.
Partner: UNT Libraries Government Documents Department

Modifications to Filling and Emptying System of Lock No. 1, Mississippi River, Minneapolis, Minnesota =: Hydraulic Model Investigation

Description: From abstract: The existing locks at Locks and Dam No. 1 were constructed between 1929 and 1932. Problems have been experienced with accumulation of ice and debris at the intakes, air entrapment in the culverts of the filling and emptying system, excessive turbulence in the lock chamber during filling, and hazardous conditions downstream from the locks during emptying operations.
Date: December 1979
Creator: Ables, Jackson H., Jr.
Partner: UNT Libraries Government Documents Department

Radioactive waste management at a Liquid Metal Fast Breeder Reactor

Description: This paper presents the radioactive waste production and management at a Liquid Metal Fast Breeder Reactor-II (EBR-II), which is operated for the US Department of Energy by the Argonne National Laboratory at the Idaho National Engineering Laboratory (INEL). Since this facility, in addition to supplying power has been used to demonstrate the breeder, fuel cycling, and recently operations with defective fuel elements, various categories of waste have been handled safely over some 14 years of operation. Liquid wastes are processed such that the resulting effluent can be discharged to an uncontrolled area. Solid wastes up to 10,000 R/hr are packaged and shipped contamination-free to a disposal site or interim storage with exposures to personnel approximately 10 mrem. Gaseous waste discharges are low such as 143 Ci of noble gases in 1978 and do not have a significant effect on the environment even with operations with breached fuel.
Date: January 1, 1979
Creator: Abrams, C.S.; Fryer, R.H. & Witbeck, L.C.
Partner: UNT Libraries Government Documents Department

First results from Mark II at SPEAR

Description: First results from the SLAC-LBL Mark II magnetic detector at SPEAR are presented. The performance of the detector is discussed and preliminary results are given on inclusive baryon production R/sub p + anti p/, R/sub ..lambda.. + anti ..lambda../, on decay modes of the D mesons and on two-photon production of eta' mesons.
Date: May 1, 1979
Creator: Abrams, G.S.; Alam, M.S. & Blocker, C.A.
Partner: UNT Libraries Government Documents Department

Results from the Mark II dectetor at SPEAR: SLAC-LBL Mark II collaboration

Description: Some recent results are presented from the Mark II detector at SPEAR: observation of some new D meson decay modes, including the Cabibbo suppressed K/sup -/K/sup +/ and ..pi../sup -/..pi../sup +/ modes, measurements of the rho ..nu.. and ..pi nu.. decays of the tau, and some new data on psi decays. 17 references.
Date: June 1, 1979
Creator: Abrams, G.S.; Alam, M.S. & Blocker, C.A.
Partner: UNT Libraries Government Documents Department

Results on two-photon interactions from Mark II at SPEAR

Description: Preliminary results on two-photon interactions from the SLAC-LBL Mark II magnetic detector at SPEAR are presented. The cross section for eta' production by the reaction e/sup +/e/sup -/ ..-->.. e/sup +/e/sup -/ eta' has been measured over the beam energy range from 2 to 4 GeV. The radiative width GAMMA/sub ..gamma gamma../(eta') has been determined to be 5.8 +- 1.1 keV (+- 20% systematic uncertainty). Upper limits on the radiative widths of the f(1270), and A/sub 2/(1310) and f'(1515) mesons have been determined.
Date: October 1, 1979
Creator: Abrams, G.S.; Alam, M.S. & Blocker, C.A.
Partner: UNT Libraries Government Documents Department

Some first results from the Mark II at SPEAR. [Branching ratio, cross sections]

Description: Preliminary results are given from the Mark II experiment at SPEAR on radiative decays of the psi' (3684) and on inclusive baryon production from 3.67 to 7.4 GeV center-of-mass energy. A 90% confidence level upper limit of 0.12% is given for BR(psi' ..-->.. ..gamma..eta'/sub c/(3455)) x BR(eta'/sub c/(3455 ..-->.. ..gamma..psi)). 10 references.
Date: June 1, 1979
Creator: Abrams, G.S.; Alam, M.S. & Blocker, C.A.
Partner: UNT Libraries Government Documents Department