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1,350 Matching Results
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Energy Matrices of the f$sup 5$ Electron Configuration
The complete electrostatic and spin-orbit matrices of the f/sup 5/ electron configuration were calculated and are presented tabularly. (auth)
Date:
September 1, 1962
Creator:
Wybourne, B. G.
Object Type:
Report
System:
The UNT Digital Library
SIZE ANALYSIS OF PARTICULATES FOUND IN AIR AT HANFORD PLUTONIUM FABRICATION FACILITIES
A study was made on the characteristics of radioactively contaminated air at Hanford work locations. One of the main objectives in this study is to define the size of particular air contamination in plutonium handling facilities. In addition to characterizing the particulate contamination, it is desirable to know the normal background particle size distribution. Data are summarized on general particle size distribution and radioactive particle distribution at two Hanford plutonium fabrication facilities. (auth)
Date:
August 1, 1962
Creator:
Selby, J.M.
Object Type:
Report
System:
The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 1, September 15, 1961 to December 14, 1961
A research program to determine the extent to which Zr and Zircaloy-2 exhibits delayed fnilure (static fatigue) as caused by absorbed H/sub 2/ and applied stress is outlined. Dynamic tensile tests were carried out on Zr and Zircaloy-2 without and wlth 200 ppm H/sub 2/. Preliminary results of a delayed failure investigation suggest that Zr containing 200 ppm H/sub 2/ is relatively insensitive to delayed ailure at room temperature up to 900 hr. (D.L.C.)
Date:
January 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Effects of Temperature on Mechanical Properties of Normal Uranium Dingot
Fatigue properties of normal uranium dingot for rotating beam specimens between 150 and 600 deg C are shown as S-N diagrams and are also given by an empirical equation of the form S = bN/sub m/, where S is the stress, N the number of cycIes, and b and m temperature dependent parameters. Tensile properties for temperatures ranging from 30 to 700 deg C are presented in tabular form and as stress-strain diagrams. All of the properties were found to decrease in value with increasing temperature except that at about 350 deg C they showed some irregularities. These irregularities can possibly be explained by the fact that at lower temperatures deformation by twinning predominates while slipping predominates sbove 350 deg C. (auth)
Date:
January 1, 1962
Creator:
Pederson, K. & Murphy, G.
Object Type:
Report
System:
The UNT Digital Library
Proceedings of the 1960 Idaho Conference on Reactor Kinetics Held at Sun Valley, Idaho, October 12-14, 1960
>Thirty papers are included on reactor kinetics with emphasis being placed on reactor safety and design considerations resulting from kinetic work. Information is presented on power excursion programs, reactor transfer function determination and application, reactor instability and thermal-hydraulic problems, and analytical methods in reactor kinetics. The accomplishments in the field and areas needing emphasis are discussed and summarized. Constructive suggestions are made on program direction and information dissemination. Separate abstracts were prepared for each paper. (N.W.R.) lOl2 Data and analytical work on various power excursion tests are summarized and discussed in order to show the present position and understanding of reactor kinetics under accident conditions. The results show that our understanding of plate-type, water-moderated systems of the low power research type seem to be in good shape. On the other hand, information on radiolytic gas formation and transient boiling phenomena is not understood too well. Data are primarily presented on safety experiments with SPERT I and KEWB; however, some information is presented on power excursion tests of Borax I, SPERT III, Triga, Treat, and Godiva. Results show that the problem of predicting the response of reactor systems is on a much firmer basis, even without knowing very much about details. …
Date:
July 1, 1962
Creator:
Haire, J. C. & Bright, G. O.
Object Type:
Report
System:
The UNT Digital Library
CALCULATIONS OF THE DOPPLER COEFFICIENT OF LARGE CERAMIC-FUELED FAST REACTORS
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 at the same fuel enrichment. Effective coarse- group elastic-removal cross sections for light elements are tabulated. It appears that, with tabulations of this sort as a guide, coarse-group sets of cross sections can be constructed to give adequate accuracy in calculations of Doppler coefficients without use of ELMOE. (auth)
Date:
August 1, 1962
Creator:
Bhide, M.G. & Hummel, H.H.
Object Type:
Report
System:
The UNT Digital Library
Radiation Problems Associated With the Handling of the Actinide Elements
The hazards connected with the handling of actinide elements are surveyed. Emphasis is placed on Th, U, Np, and Pu. It is pointed out that the chemical toxicity of the actinides is usually minor when compared with radiochemi cal toxicity. Inhalation and ingestion are the important routes of entry but direct injection into the blood stream through wounds also requires consideration. Special enclosures, such as glove boxes, function primarily to minimize the risk of inhalation and aid in confinement. The external hazard from actinide elements, primarily due to gamma and fast neutron emission, varies considerably with the element and its source. Irradiated actinides, such as Th and Pu, usually show an increase in the external hazard from gamma radiation with extent of irradiation. (C.H.)
Date:
April 1, 1962
Creator:
Steindler, M.J.
Object Type:
Report
System:
The UNT Digital Library
A FORTRAN Program for Calculating Single Crystal Absorption Corrections
A Fortran program is described for calculating the absorption correction for application to single crystal x ray or neutron intensity measurements. The program is available in the form of symbolic punched cards. InstrucPions are included. (J.R.D.)
Date:
April 1, 1962
Creator:
Wehe, D. J.; Busing, W. R. & Levy, H. A.
Object Type:
Report
System:
The UNT Digital Library
Calculation of Distance Factors for Power and Test Reactor Sites
>Reference information and guidance on procedures and basic assumptions related to reactor siting are presented which can be used to calculate distance requirements consistent with current siting practices. A single method of competing distances and exposure for a general class of reactors is giveo. (J.R.D)
Date:
January 1, 1962
Creator:
DiNunno, J. J.; Anderson, F. D.; Baker, R. E. & Waterfield, R. L.
Object Type:
Report
System:
The UNT Digital Library
THE DISTORTED-WAVE THEORY OF DIRECT NUCLEAR REACTIONS. I. "ZERO-RANGE" FORMALISM WITHOUT SPIN-ORBIT COUPLING, AND THE CODE SALLY
The distorted-wave theory of direct nuclear reactions is presented in a unified manner, in which the effects of assuming various reaction mechanisms and nuclear models appear only in certain radial form factors. The zero-range approximation is used, and spin-orbit coupling is neglected in the distorted waves. Formulas are given for transition amplitudes, cross sections, and polarizations. A description is given of the IBM-704 computer code SALLY that is based on these formulas. (auth)
Date:
February 1, 1962
Creator:
Bassel, R.H.; Drisko, R.M. & Satchler, G.R.
Object Type:
Report
System:
The UNT Digital Library
HOMOGENIZATION OF MOLTEN-SALT REACTOR PROJECT FUEL SAMPLES
A copper pulverizer-mixer was designed for homogenizing Molten-Salt Reactor Project (MSRP) fuel. The copper sampling ladle that contains the solidified fuel is placed in the pulverizer-mixer, which is agitated on a mixer mill. The fuel is fractured out of the ladle, pulverized into a homogeneous powder, and transferred to a storage bottle. The homogenized fuel sample is then available for analysis. (auth)
Date:
July 1, 1962
Creator:
Gaitanis, M.J.; Lamb, C.E. & Corbin, L.T.
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
HYDROLOGIC AND GEOLOGIC STUDIES FOR PROJECT GNOME. Preliminary Report
Geologic lnformation required to define the pre- and post-shot physical and chemical characteristics of the sait and other rocks affected by the exploslon was gathered. Information on the pre- and post-shot hydrologic condltlons at the site and the surrounding area was also obtalned. (M.C.G.)
Date:
February 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks
Thermal-stress and strain-fatigue analyses of the MSRE fuel and coolant pump tanks were completed for determining the quantity of coollng air required to obtain the maximum life of the pump tanks and to determine the acceptability of the pump tanks for the intended service of 100 heating cycles from room temperature to 1200 deg F and 500 reactor power-change cycles from zero to 10 Mw. A cooling-air flow rate of 200 cfm for the fuel pump tank was found to be an optimum value that provided an ample margin of safety. The coolant pump tank was found to be capable of the required service without air cooling. (auth)
Date:
October 1, 1962
Creator:
Gabbard, C.G.
Object Type:
Report
System:
The UNT Digital Library
FACILITY FOR PHOTOGRAPHING IN-PILE MELTDOWN EXPERIMENTS IN TREAT
Techniques and equipment were developed for photographing of samples during in-pile meltdown experiments in TREAT. The design and materials for the transparent meltdowm facility are described. The procedures for assemblys insertion in TREAT, removal, and disassembly are outlined. (M.C.G.)
Date:
January 1, 1962
Creator:
Golden, G.H.; Dickerman, C.E. & Robinson, L.E.
Object Type:
Report
System:
The UNT Digital Library
Experimental Breeder Reactor-II (EBR-II) Shield Design
A description of the EBR-II shield and the methods employed in arriving at the final design are presented. The major shield design problems for that reactor are enumerated and discussed. (auth)
Date:
September 1, 1962
Creator:
Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
Object Type:
Report
System:
The UNT Digital Library
Nonequilibrium Ionization in Magnetohydrodynamic Generators
The steady state ionization of a gas in which the electrons are hot and the atoms cool is investigated. The rate equations governing ionization, excitation, recombination, and de-excitation are solved for a model system using rate coefficients appropriate to the Cs atom. Included are all processes involving free electrons as well as spontaneous emission and resonance trapping of radiation. No incoming radiation is assumed, and the system is assumed large compared with a collisional mean free path but optically thin except for resonance radiation. The fractional ionization is computed for a range of electron temperatures and Cs densities of interest in MHD studies. It is found that there are reasonable conditions of temperature and density under which the ionization is close to that which would prevail if the system were in equilibrium at the electron temperature. At lower temperatures or densities, the ionization decreases but is still much greater than that appropriate to the gas temperature. (auth)
Date:
January 1, 1962
Creator:
BenDaniel, D.J. & Tamor, S.
Object Type:
Report
System:
The UNT Digital Library
A Theoretical Study of Destructive Nuclear Bursts in Fast Power Reactors
The calculation of destructive nuclear bursts in fast reactors by an improved Bethe-Tait method, which, for purposes of calculation, neglects propagation of the pressure wave is described. TMen exact numerical calculations for hydrodynamic and neutronic conditions during the power burst are performed in order to assess the importance of this neglect. (auth)
Date:
February 1, 1962
Creator:
Jankus, V. Z.
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
Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962
During the report period 110 Mw-hr of operation were completed by LAMPRE I at various power levels, and observations were made of control element performance and reactivity losses. Metallographic examination of a Core I capsule having 120 Mw-hr of irradiation exposure disclosed no major attack. Core II utilizes Ta alloy melts and 13 fuel melts. Starting materials for Core II capsules are tabulated. In research and development a gamma-ray conversion television was used to observe the flow of molten Pu in the PTA experiment. Dilute fuels being studied for use in a high-performance reactor include Pu --Co - -Ce alloys, ing exposure of test containers to U --Pu -Mn fuel at 900 deg C for 2 hrs are tabulated. In fuel reprocessing data on decontamination of Pu metal by electrorefining and by solvent extraction were obtained. Details of maintenance and development of the core test facility are included. (J.R.D.)
Date:
June 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Quarterly Status Report on LAMPRE Porgram for Period Ending August 20, 1962
Operation of the Lampre I during the report period is described and data on the operating history of this reactor are summarized. Other work is reported on core calculations, fuel and container development, and compatibility of Pu-Co- Ce alloys with Ta. Studies of the physical properties of Pu alloys with C, ln, Si, and rare earths are described. Data on the room temperature densities in the Pu-Ce-Co alloy system are presented. Solvent extraction studies concerning separation of Pu are included along with results of electrorefining of irradiated Pu fuels. The developmental status of the core test facility is reported. (J.R.D.)
Date:
September 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SPECIFIC HEAT DATA ANALYSIS PROGRAM FOR THE IBM 704 DIGITAL COMPUTER
A computer program was developed to calculate the specific heat of a substance in the temperature range from 0.3 to 4.2 deg K, given temperature calibration data for a carbon resistance thermometer, experimental temperature drift, and heating period data. The speciftc heats calculated from these data are then fitted by a curve by the methods of least squares and the specific heats are corrected for the effect of the curvature of the data. The method, operation, program details, and program stops are discussed. A program listing is included. (M.C.G.)
Date:
January 1, 1962
Creator:
Roach, P.R.
Object Type:
Report
System:
The UNT Digital Library
SALT PHASE CHLORINATION OF REACTOR FUELS. III. CATALYZED DISSOLUTION OF URANIUM DIOXIDE IN LEAD CHLORIDE-CHLORIDE SYSTEMS
The rapid dissolution of uranium dioxide is described, wherein copper is added to molten lead chloride at 550 deg C. and chlorine is passed through the melt. The integral dissolution of zirconium-clad uranium dioxide fuels is also described. The dissolution rate of uranium dioxide is directly proportional to the concentration of cuprous chloride if an excess of chlorine is used; the value for the rate constant is approximately 100 mg (UO/sub 2/) cm/sup -2/ min/sup -1/ (CuCl molality). The uranium dioxide is converted to water soluble uranyl chloride. The dissolution rate can be controlled by three factors: the copper concentration, the flow rate of chlorine, and the surface area of uranium dioxide. Scoping work indicates that iron chloride may be as effective catalytically as copper chloride for uranium dioxide dissolution in the lead chloride -chlorine system at 550 deg C; thallium chloride is not as effective. (auth)
Date:
February 1, 1962
Creator:
Vander Wall, E. M.; Bauer, D. L. & Hahn, H. T.
Object Type:
Report
System:
The UNT Digital Library
AN ENERGY MEASUREMENT OF PuF$sub 4$ NEUTRONS AND THE NEUTRON DOSE RATE FROM PuF$sub 4$ PROCESSING EQUIPMENT
By use of the multisphere neutron spectrometer, the neutrons emitted from a sample of PuF4 were analyzed for average neutron energy. The results indicated an average neutron energy of 1.25 plus or minus 0.25 Mev. The room background had a fast neutron energy of 1.00 plus or minus 0.25 Mev, with a reasonably large contribution from scattered neutrons. A 110 gram sample of PuF/ sub 4/ gave a dose rate reading of about 9 mrem/hr at a distance of 30 cm, which corresponds to a neutron yield of 8.0 x 10/sup 5/ n/sec. The room background was about 0.5 mrem/hr. Neutrons originating in the PuF/sub 4/ processing equipment were measured with the 10 inch sphere neutron survey instrument. Comparable readings were obtained with the converted PeeWee neutron survey instrument by using a correction factor of 30, or a fast neutron energy of 0.5 or 0.4 Mev. Either of these factors enabled a monitor to obtain a more accurate dose rate with the PeeWee than was previously possible. (auth)
Date:
May 1, 1962
Creator:
Hankins, D.E.
Object Type:
Report
System:
The UNT Digital Library