140 Matching Results

Search Results

Results: 1 - 24 next
open access

333 Building preliminary survey potential equipment improvements

Description: In order to provide advance direction for 333 Building equipment development work, a survey of potential areas of significant savings through equipment improvement has been made. The purpose of this report is only to indicate areas for investigation, not to define a program. Equipment is adequate to maintain operating continuity and provide for safe operation of the building. Special attention should be given to ``one-of-a-kind`` pieces of equipment. These include the press, cutoff saw, beta he… more
Date: August 22, 1962
Creator: Drumheller, K.
Partner: UNT Libraries Government Documents Department
open access

Accidental nuclear excursion Recuplex operation 234-5 facility. Final report: Date of incident: April 7, 1962

Description: On Saturday morning, April 7, 1962, at about 1059 Armed Forces time, an accidental nuclear excursion occurred in the plutonium waste recovery facility (Recuplex) of the 234-5 Building. This excursion did not result in any mechanical damage or spread of contamination. Three employees of the General Electric Company received overexposures to gamma and neutron radiation. None were fatally exposed; in each case the overexposure was recognized promptly, and following medical observation and testing … more
Date: August 1, 1962
Partner: UNT Libraries Government Documents Department
open access

Acid-Base Equilibria in Tertiary Butyl Alcohol

Description: From abstract: "The dissociation of acids in tertiary butyl alcohol has been studied by potentiometric, spectrophotometric, and conductimetric methods. Values for the over-all dissociation of perchloric and picric acids and several tetrabutylammonium salts were estimated by the Fuoss-Kraus treatment of conductance data. Potentiometric studies were carried out at constant ionic strength in order to minimize activity coefficient variations. An acidity scale was established from potentiometric mea… more
Date: August 6, 1962
Creator: Marple, Leland & Fritz, James S. (James Sherwood), 1924-
Partner: UNT Libraries Government Documents Department
open access

Administration of ORNL Research Reactors

Description: Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)
Date: August 20, 1962
Creator: Casto, W. R.
Partner: UNT Libraries Government Documents Department
open access

Aeroradioactivity Survey and Areal Geology of Parts of East-Central New York and West-Central New England (ARMS-I)

Description: Report concerning "[a]n airborne gamma-radiation survey of Connecticut, Rhode Island, and parts of New York, Massachusetts, New Hampshire, and Vermont" (p. 5) made between 1958 and 1960 that indicated that a broad range of radioactivity exists in those areas depending on the type of bedrock. Correlations are drawn between this radioactivity and the geology of the region.
Date: August 1962
Creator: Popenoe, Peter
Partner: UNT Libraries Government Documents Department
open access

An Analysis of the Inherent Stability of the EOCR

Description: The inherent stability of the EOCR at full power, exclusive of the heat exchanger, is investigated. Space and time dependent differential equations and transfer functions for the nuclear and thermal processes occurring in the reactor core and vessel are derived. Reactor stability is analyzed by application of the Nyquist stability criterion. The results show that the EOCR has an extremely large margin of inherent stability. (auth)
Date: August 24, 1962
Creator: Gossmann, S.R.
Partner: UNT Libraries Government Documents Department
open access

Analytical Studies of Transient Effect in Fast Reactor Fuels: [Part] 1

Description: From abstract: "An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined and possible mechanisms of failure are analyzed."
Date: August 1962
Creator: Osborn, R. B. & Sherer, D. B.
Partner: UNT Libraries Government Documents Department
open access

Annual Progress Report on Fuel Element Development for FY 1962

Description: Activities in a project aimed at the improvement of fuel elements for high flux test reactors are reported. The investigation of new fuel compositions, distributions, and geometries is being undertaken to increase fuel life, to improve the flux distribution, and to provide a means of safely reaching higher reactor operating power and power density in these reactors. The effects of nuclear irradiation on the fuel and structural materials is being studied to predict the performance of these mater… more
Date: August 15, 1962
Creator: Gibson, G. W. & Francis, W. C.
Partner: UNT Libraries Government Documents Department
open access

Application of Distillation Techniques to Radiochemical Separations

Description: Nuclear Science Series'' of the National Research Council. Committee on Nuclear Science. The use of vacuum distillation of inorganic compounds and metals for radiochemical separations is reviewed. A brief description of the experimental apparatus which is most often used for the distillation is outlined. Advantages and disadvantages of the various techniques are discussed. Detailed separation procedures are described for wet chemical distillation separations as well as for separations of daught… more
Date: August 1, 1962
Creator: DeVoe, J. R.
Partner: UNT Libraries Government Documents Department
open access

BEAM TRANSPORT. A Selected, Annotated Bibliography

Description: References applicable to the problems of transponting charged particles in the areas external to accelerators are presented. The 891 references cover the period 1949 to 1981, with a few references both prior and subsequent to this period included. Part I is concerned with the more general aspects of electron optics. Part II contains the references that deal more directly with applications to particle accelerators. Arrangement within each pant is by broad subject with cross references listed at … more
Date: August 1, 1962
Creator: Kepple, R.R.
Partner: UNT Libraries Government Documents Department
open access

Bibliography on Atomic Transition Probabilities

Description: Report presenting a bibliography on atomic transition probabilities. The papers are arranged according to elements and stages of ionization, and the method employed and class of transitions are indicated behind each reference. Only articles on discrete transitions, both permitted and forbidden, are listed. Also included is a supplementary list of papers dealing with transition probabilities from a general point of view, a table showing the availability of numerical material on the individual at… more
Date: August 1, 1962
Creator: Glennon, B. M. & Wiese, W. L.
Partner: UNT Libraries Government Documents Department
open access

Boundary Effects in Rotating-Plasma Experiments

Description: The problem of current continuity and viscous drag at the boundaries in rotating-plasma experiments is discussed. A hypothetical model having a steady state with axial symmetry is emphasized; it is shown that the discharge impedance derived from this model does not agree with many observations. The Homopolar III'' experiment is described in which the flux surfaces were strongly convex and parallel to the toroidal-shaped electrodes. In this way friction at the insulators was reduced. But the str… more
Date: August 1, 1962
Creator: Kunkel, W.B.; Baker, W.R.; Bratenahl, A. & Halbach, K.
Partner: UNT Libraries Government Documents Department
open access

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Description: Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Date: August 1962
Creator: Hanthorn, H. E.
Partner: UNT Libraries Government Documents Department
open access

CALCULATIONS OF THE DOPPLER COEFFICIENT OF LARGE CERAMIC-FUELED FAST REACTORS

Description: ABS>Calculations of the Doppler coefficient of large, ceramicfueled fast reactors containing plutonium were made by means of the ELMOE program to provide accurate flux calculations. The temperature-dependent cross sections of P. Greebler et al., for U/sup 238/ and Pu/sup 239/ were used. Doppler coefficients of the order of 10/sup -5/ ntermediate tem k/ C were obtained, in agreement with Greebler's results. Coefficients of carbide fueled reactors are about 0.7 of those of oxide-fueled reactors a… more
Date: August 1, 1962
Creator: Bhide, M.G. & Hummel, H.H.
Partner: UNT Libraries Government Documents Department
open access

Capsule Irradiation of Unalloyed Uranium at High Temperatures

Description: Abstract: Cast and Wrought specimens and restrained wrought specimens of unalloyed uranium were irradiated in the Materials Testing Reactor, as the first in a series of experiments to develop fuel materials for sodium cooled reactors.
Date: August 15, 1962
Creator: Harrington, D. G. & Newton, J. B.
Partner: UNT Libraries Government Documents Department
open access

CARBIDE FUEL DEVELOPMENT. Progress Report, April 1, 1962 to June 30, 1962

Description: All of the UC-PuC powder required for the natural U irradiation specimens, and some of the powder required for the enriched U irradiation specimens was synthesized. All of the natural uranium UC-PuC pellets required were fabrlcated by pressing and sintering, and are being ground to size. The average density of the (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ pellets was 12.54 g/cm/ sup 3/ (92.4% of theoretical) and of the (U/sub 0.08/Pu/sub 0.2/)C/sub 0.95/ plus 0.1 wt% Ni pellets was 13.15 g/cm/sup 3 (9… more
Date: August 10, 1962
Creator: Strasser, A. & Taylor, K.
Partner: UNT Libraries Government Documents Department
open access

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, APRIL-JUNE 1962

Description: Research and development progress is reported on chemical-metallurgical processing, fuel cycle applications of voiatility and fluidization techniques, calorimetry, reactor safety, energy conversion, determination of nuclear constants, and routine operations. (M.C.G.)
Date: August 1, 1962
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department Monthly Report: July 1962

Description: This report, for July 1962 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and safety and security.
Date: August 20, 1962
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

Chemical Technology Division, Unit Operations Section Monthly Progress Report, February 1962

Description: In the operation of 6-in.-dia. foam-liquid columns, increase in either the liquid flow or foam flow caused increased channeling with increased HTU. Flooding values for the Immi mixer-settler were obtalned using the amine extraction final cycle Pu flowsheet. Two tests of the addltlon of uranyl nitrate to a thoria sol were made, one of which gave a good product and the other a product which disintegrated during calcination. Material balances for 22 waste calcination runs are summarized. (auth)
Date: August 23, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
open access

Chemistry of Cement: Proceedings of the Fourth International Symposium, Volume 1, 1960

Description: Document containing principle and supplementary papers presented at the Fourth International Symposium on the Chemistry of Cement, as well as discussions of those papers by members of the Symposium. Index begins on page 551.
Date: August 31, 1962
Creator: United States. National Bureau of Standards.
Partner: UNT Libraries Government Documents Department
open access

Concentration and Velocity Profiles in a Stefan Diffusion Tube

Description: The Stefan diffusion tube was widely used as a means of determining vapor-phase diffusion coefficients. By this method the diffusion coefficient was calculated on the asaumption of plug-flow (flat) concentration and velocity profiles in the diffusion tube. These assumptions were examined theoretically and experimentaily in this study. The theoretical study and the experimental results indicated that the concentration profile is flat across the diffusion tubs. The veloctty profile was found to b… more
Date: August 16, 1962
Creator: Heinzelmann, F. J.; Wasan, D. T. & Wilke, C. R.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen