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219
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181
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35
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26
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25
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21
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19
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1,269 Matching Results
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Organic Nuclear Reactors: An Evaluation of Current Development Programs
Organic reactor technology is critically evaluated and areas of research and development work now lacking or inadequate for the successful development of this reactor concept are indicated. The development programs for present organic and heavy water moderated concepts appear generally adequate to reach specific goals. However, the narrow scope of the organic reactor program should be broadened to assure coverage of areas where the application of novel principles might result in marked economic benefits. Further work, principally of a basic nature, is recommended in the fields of chemistry, processing, management, and thermodynamic properties of coolants, in fuel development, and in concept evaluation. (N.W.R.)
Date:
May 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
The Electrical Resistivity of Molten and Solid Thorium-Magnesium Eutetic
Electrical resistivity properties of polycrystalline 39 wt % thorium-- magnesium eutectic are reported for the solid from room temperature to its melting point at 589 deg C and as a liquid from its melting point to 900 deg C. The electrical resistivity of the eutectic at the melting point was 69.5 microhm- centimeters; it decreased to a value of 64.8 microhm-centimeters at 900 C. Tantalum tubing was used to contain the alloy in the molten state. (auth)
Date:
May 1, 1962
Creator:
Provow, D. M. & Fisher, R. W.
Object Type:
Report
System:
The UNT Digital Library
A THEORETICAL STUDY OF SIMPLE MANY-ELECTRON SYSTEMS
None
Date:
May 1, 1961
Creator:
Sachs, L.M.
Object Type:
Report
System:
The UNT Digital Library
2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE
Given multigroup fluxes and adjoint fluxes of any cylindrical R-Z configuration, 2D PERT may compute: the prompt-neutron lifetime; the relative worth of various delayed neutrons; the integrals of capture, fission, etc., of given materials over any given region; local perturbations, i.e., danger coefflcients; and integrated perturbations, i.e., reactivity effect of uniform variation in the cross sections affecting a whole region. 2D PERT is programmed for a 32K IBM-704 using 3 tape units. The code is written in FORTRAN with the exception of two SAP subroutines. Input fluxes and adjoint fluxes are on tapes which may be obtained either directly from CUREM output or manufactured by a special tape-writing routine. Homogeneous cross sections and variations of these cross sections are either read in as input information or are computed by the code from a microscopic-cross-section library and atomic densities given as input. A combination of these methods may be used. (auth)
Date:
May 1, 1962
Creator:
Chaumont, J. M. & Koerner, J. A.
Object Type:
Report
System:
The UNT Digital Library
Sodium Fluozirconate Precipitation Process for Zirconium Fuels. Part 1. Laboratory Development
Precipitation, evaporation, and extraction feed preparation conditions are established for the removal of zirconium and fluoride from fuel dissolver product solutions by the addition of sodium formate. A sparingly soluble complex fluozirconate is formed. Ninety-five to 99% of the zirconium and fluoride is separated from the uranium losses of 0.1% or less. Chemical material balances, based on experimental data, were developed for two flowsheets. In one flowsheet, sufficient nitric acid is added to the combined wash solution and filtrate produced during the precipitation step to destroy the formate ion (which inhibits uranium extraction) and to prevent post-precipitation during the evaporation of these solutions. The other flowsheet calls for addition of sufficient nitric acid to destroy the formate ion, but not enough to prevent post- precipitation during the concentration step. Post-precipitation removes additional zirconium and fluoride, but necessitates an additional solids- separation step. (auth)
Date:
May 15, 1962
Creator:
Newby, B. J.
Object Type:
Report
System:
The UNT Digital Library
REACTIVITY CALIBRATIONS AND FISSION-RATE DISTRIBUTIONS IN AN UNMODERATED, UNREFLECTED URANIUM-MOLYBDENUM ALLOY RESEARCH PROGRAM
Completion of zero-power critical experiments with the ORNL Health Physics Research Reactor is reported. A description is given concerning these experiments which were used to determine the critical size, fission-rate distributions, reactivity calibrations of its movable parts, the temperature coefficient of reactivity, and the reactivity effects of the presence of neutron- reflecting materials adjacent to the reactor. (J.R.D.)
Date:
May 10, 1962
Creator:
Mihalczo, J.T.
Object Type:
Report
System:
The UNT Digital Library
The in-Pile Thermal Conductivity of Selected ThO$Sub 2$--UO$Sub 2$ Fuels at Low Depletions
None
Date:
May 1969
Creator:
Jacobs, D. C.
Object Type:
Report
System:
The UNT Digital Library
Compensation for Victims of Crimes of Violence
This report details the compensating schemes of victims of comes of violence. It was announced on June 24, 1964, and came into operation on August 1, 1964.
Date:
May 31, 1966
Creator:
Price, Hugh P.
Object Type:
Report
System:
The UNT Digital Library
Powers of the President
This report is about the powers of the President.
Date:
May 6, 1969
Creator:
Tansill, William R.
Object Type:
Report
System:
The UNT Digital Library
Powers Of The President
This report consists of the powers of president.
Date:
May 6, 1969
Creator:
Tansill, William R.
Object Type:
Report
System:
The UNT Digital Library
Poll Taxes Levied By States
This report documents how every state deals with the poll tax, and the effect of the poll tax on the voting rights of citizens.
Date:
May 6, 1965
Creator:
Thornton, Robert L.
Object Type:
Report
System:
The UNT Digital Library
Major developments in United states foreign policy during the Kennedy administration, January 20 1961-November 23 1963: A brief selected chronology.
This report is about developments in the United States during the Kennedy administration.
Date:
May 18, 1967
Creator:
Whelan, Joseph G.
Object Type:
Report
System:
The UNT Digital Library
The military-industrial complex. A current reading list. 1969
This report consists of list of the military-industrial complex.
Date:
May 20, 1969
Creator:
Browne, Marjorie Ann
Object Type:
Report
System:
The UNT Digital Library
Erroneous Predictions and Negative Comments Concerning Exploration, Territorial Expansion, Scientific and Technological Development; Selected Statements
This report documents articles that opposed events, buildings, or inventions that are now historically or modernly important, such as the Louisiana Purchase or the invention of the airplane.
Date:
May 29, 1969
Creator:
Gamarra, Nancy T.
Object Type:
Report
System:
The UNT Digital Library
Domestic distribution of USIA materials: A Summary of Pros and Cons
This report is a summary of Pros and Cons of domestic distribution of USIA materials.
Date:
May 8, 1969
Creator:
Collier, Ellen C.
Object Type:
Report
System:
The UNT Digital Library
Environment, Natural Resources and Population
This report includes Findings and recommendations of a study about Environment, Natural Resources and Population conducted by the committee on Resources and Man of the National Academy of Sciences-National Research Council (NAS-NRC).
Date:
May 2, 1969
Creator:
Bowman, Wallace D.
Object Type:
Report
System:
The UNT Digital Library
Postwar Presidents and the Senate Foreign Relations Committee, 1969.
This report is about the President-Senate foreign relations committee relationship.
Date:
May 6, 1969
Creator:
Collier, Ellen C.
Object Type:
Report
System:
The UNT Digital Library
Material Buckling Measurements on Graphite-Uranium Systems at Hanford: A Summary Tabulation
Measurements of material bucklings for graphite uranium systems are summarized. A comprehensive listing and guide to the original data sources is provided. Complete information on physical and nuclear properties of the lattice and the geometry of the exponential assembly is included, along with some of the auxiliary data taken. The fuel sizes vary from 0.925 to 2.5 in. in diameter for five different fuel geometries. The lattice spacings vary from 4 3/16 to 15 in. Over 300 measurements of material buckling are included. (auth)
Date:
May 1, 1961
Creator:
Wood, D. E.
Object Type:
Report
System:
The UNT Digital Library
HEAD-END TREATMENT OF LOW LEVEL WASTES PRIOR TO FOAM SEPARATION
Calcium-magnesium precipitation apparatus was used to reduce the concentrations of these elements in ORNL tap water, used as a substitute for waste water of low level of radioactivity, prior to strontium removal by foam separation. With and without alkali and flocculator chambers and with a stirred sludge of ratio height to diameter equal to 1/1 to ~4/1, use of 5 x 10/sup -3/ M each of NaOH and Na/sub 2/CO/sub 3/ and 2 ppm Fe/sup 3+/ reduced the dissolved Ca + Mg concentrations to 1 to 2 ppm as calcium. Simultaneously, a strontium DF of 20 to 200 was achieved, and, by adding Grundite clay in the proportion ~0.5 1b/ 1000 gal, a cesium DF of 10 to 40 was achieved. (auth)
Date:
May 29, 1962
Creator:
Schonfeld, E. & Davis, W. Jr.
Object Type:
Report
System:
The UNT Digital Library
CHEMICAL EFFECTS OF HIGH EXPLOSIVE SHOCK WAVES ON VARIOUS COMPOUNDS WHICH OCCUR IN THE GNOME CONTAINMENT MEDIUM
None
Date:
May 1, 1962
Creator:
Bond, W.D.
Object Type:
Report
System:
The UNT Digital Library
Calculation and Measurement of the Transient Temperature in a Low- Enrichment UO$sub 2$ Fuel Rod During Large Power Excursions
The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element are presented. The tests were performed to investigate the possibility of damage to such long thermal-time-constant fuel rods when subjected to short-period power excursions, and to test the effectiveness of an instrumentation technique for measurement of UO/sub 2/ fuel temperatures within the rods. In an initial series of power excursion tests, in which the range of reactor periods was from approximately 1 sec to 7.5 msec, simultaneous measurements were made of the transient temperature at the center of the fuel rod and at the outer cladding surface. Fuel rod rupture occurred during the exponential rise of the 7.5-msec excursion. Similar short-period tests performed on a second fuel rod contain ing no internal thermocouples did not result in cladding failure, supporting the postulation that rupture of the first rod was caused by waterlogging of the UO/sub 2/ as a result of the cladding penetrations made for installation of the internal thermocouples. Calculations of the transient temperature distribution in the fuel rod were made, and the results are found to be in good agreement with the experimental data obtained on the central-UO/sub 2/ and cladding-surface …
Date:
May 18, 1962
Creator:
Houghtaling, J. E.; Quigley, T. M. & Spano, A. H.
Object Type:
Report
System:
The UNT Digital Library
BIOLOGICAL AND MEDICAL RESEARCH DIVISION SUMMARY REPORT, JANUARY-DECEMBER 1960
Separate abstracts were prepared for 43 sections of this report. (C.H.)
Date:
May 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
CLIP 1--AN IBM-704 PROGRAM TO SOLVE THE P-3 EQUATIONS IN CYLINDRICAL GEOMETRY
A second order form of the cylindrical P-3 equations is obtained for the case of an isotropic source. The boundary conditions and numerical method are discussed. Input preparation and operating instructions are included. (auth)
Date:
May 1, 1962
Creator:
Anderson, B.; Davis, J.; Gelbard, E.; Jarvis, P. & Pearson, J.
Object Type:
Report
System:
The UNT Digital Library
A System for Generating Gamma Ray Cross Section Data for Use with the IBM-7090 Computer
A system for generating detailed tables of gamma ray cross section data has been devised for use on the IBM7090 computer. This sy;tem obviates the preparation of large amounts of cross section data. It also provides a scheme for rapid access to these tabulated values. (auth)
Date:
May 16, 1962
Creator:
Penny, S. K.; Emmett, M. B. & Trubey, D. K.
Object Type:
Report
System:
The UNT Digital Library