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The Effect of Radiation and Nitric Acid-Nitrate Salt Solution on Some Non- Metallic Materials

Description: Several plastic materials and one ceramic alumina were tested for possible use as electrical insulators and spacers in an electrolytic dissolver for processing irradiated nuclear fuels. They were first screened for chemical resistance to the boiling dissolver product solution composed of 1 M nitric acid and 75 g/l stainless steel metal components as nitrates. Those that were resistant were then exposed simultaneously to the boiling dissolver product solution and a gamma irradiation field. Value… more
Date: December 10, 1962
Creator: Decker, L. A.
Partner: UNT Libraries Government Documents Department
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View Factors for Heat Radiation in Ghgr Core Configuration

Description: An analysis dealing with view factors is presented in an investigation of the overall interchange factors for heat radiation. Examples concerning the EGCR and the Peach Bottom Reactor are included. (J.R.D.)
Date: December 10, 1962
Creator: Landoni, J. A.
Partner: UNT Libraries Government Documents Department
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HIGH-TEMPERATURE VAPOR-FILLED THERMIONIC CONVERTER. Quarterly Technical Progress Report, July 1 through September 30, 1962

Description: The post-test analysis of Cell E was completed with the exception of the microprobe analysis of the emitter structure. Interpretation of data from the analysis indicated the necessity of improving the cleanliness of future cell assemblies and especially the need for techniques to determine the emitter condition throughout final assembly. A 10 UC-90 ZrC emitter was installed in Cell F. Thermocouple installation and calibration and high-temperature vacuum emission tests are being conducted prior … more
Date: November 10, 1962
Creator: Godsin, W.
Partner: UNT Libraries Government Documents Department
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Monte Carlo status report

Description: No Description Available.
Date: November 10, 1962
Creator: Capo, M.A.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium : Summary Report, September 15, 1961 to September 14, 1962

Description: The following report summarizes an investigation made to determine the extent to which zirconium and zirconium alloys exhibit delayed failure as caused by a combination of absorbed hydrogen and applied stress during the period September 15, 1961, to September 14, 1962.
Date: October 10, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962

Description: The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedepe… more
Date: October 10, 1962
Creator: Weinstein, D. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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The Fabrication and Irradiation Testing of Dispersion-Type BeO-UO$sub 2$ Ceramic Fuel Materials

Description: Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The results of measurements made to study the effect of fuel loading on the properties of the fuel bodies and the results of irradiation tests of fuel pellets composed of 20 vol% UO/sub 2/ dispersed in BeO are presented. Experience in the fabrication of dispersion-type BeO --UO/sub 2/ ceramic fuel materials is described. From the results obtained, it is believed that BeO --UO/sub 2/ fuel materials of th… more
Date: October 10, 1962
Creator: Johnson, D. E. & Lofftus, F. H.
Partner: UNT Libraries Government Documents Department
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SAMOOM code

Description: No Description Available.
Date: October 10, 1962
Creator: Duckworth, G. D. & Sullivan, F. E.
Partner: UNT Libraries Government Documents Department
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Future Program for the Cern PS and the Brookhaven AGS

Description: The alternating-gradient proton synchrotrons at CERN and Brookhaven are very similar in size, design and in their experimental use. For this reason, collaboration between the groups at CERN and Brookhaven has been close throughout the history of these two machines. For the most part this has taken the form of exchanges of visits of individual machine designers and of high-energy physicists. By 1962, however, it appeared that the reciprocal flow of information was not adequate and a more formal … more
Date: 1962-09-10/1962-09-14
Creator: Blewett, J. P.; Bittner, J. W.; Brown, H. N. & Maschke, A. W.
Partner: UNT Libraries Government Documents Department
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Magnetic Properties of Some Intra-Rare Earth Alloys

Description: Technical report. From Abstract : "Paramagnetic susceptibilities of samarium structure alloys in the systems La-Gd, Nd-Y, Nd-Tm, and Ce-Y were measured from 4.2 - 300°K to determine what effect the formation of this structure has on the magnetic properties of the alloys. Susceptibility maxima were observed in the Nd-Y and Nd-Tm alloys, at 34.5 and 28.5°K, respectively. Slope changes were observed in the curve of 1/x versus T for the La-Gd alloy at 155 and 130°K, and the susceptibility of this a… more
Date: September 10, 1962
Creator: Roughan, P. E. & Deane, A. H.
Partner: UNT Libraries Government Documents Department
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The Ornl Analytical Chemistry Division's 150-Kv Cockcroft-Walton Generator

Description: A general description of the facilities used to house a small Cockcroft- Walton generator is presented. Preliminary irformation and data are given as to the operational performance of the generator, the radiation safety controls involved, and the expected use of the device, In addition, an automatic-manual device for control of tritium target usage is described. (auth)
Date: September 10, 1962
Creator: Strain, J. E.; Hampton, W. J. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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The Overpressure-Duration Relationship and Lethality in Small Animals. Technical Progress Report

Description: A total of 993 mice, rats, guinea pigs, and rabbits were exposed to sharp-rising overpressures of various short durations. They were mounted on a concrete pad above which high-explosive charges, ranging in weight from 0.50 oz to 64 lbs, were detonated. Pressure-time measurements were obtained with pencil- type and shock-tube piezo-electric gauges on the pad directly beneath the charges. The duration of the blast waves ranged from 0.40 to 6.8 msec. The LD/sub 50/ pressures were calculated for ea… more
Date: September 10, 1962
Creator: Richmond, D. R.; Goldizen, V. C.; Clare, V. R. & White, C. S.
Partner: UNT Libraries Government Documents Department
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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
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DISCUSSION OF AN ACTIVATION METHOD FOR MEASURING THE RATIO OF U$sup 238$ ABSORPTION TO U$sup 235$ FISSION IN A REACTOR

Description: The theory is presented in detail of an activation method for measuring the ratio of U/sup 238/ absorptions to U/sup 235/ fissions in a nuclear reactor. The origin of the activities is discussed, the equations are given for interpretation of the measurements, and the expected counting rates are computed for a typical experiment in the EGCR. (auth)
Date: August 10, 1962
Creator: Preskitt, C.A.
Partner: UNT Libraries Government Documents Department
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Evaluation of lithium as a control rod poison

Description: To permit more accurate evaluation of the incentives for isotopes producing control rods a determination was performed of the tritium production which would result from conversion to lithium HCR`s. A cursory examination of the gains resulting from the use of lithium shows that a significant amount of tritium could be produced in this manner totaling 1.6 percent of the present Pu-239 production on an atom equivalent basis.
Date: August 10, 1962
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Loading and Elution Characteristics of Some Natural and Synthetic Zeolites

Description: The cation exchange characteristics of several commercially available zeolites were evaluated, Equilibrium loading characteristics and exchange capacities were determined experimentally in the binary systems cesium-lithium, cesium-- sodium, cesium--potassium, cesium-Tubidium, cesium -- hydrogen, cesium-- ammonium, strontium-- magnesium, strontium-- calcium, strontium-- barium, and strontium-- hydrogen for several zeolites. Exchangeable cation fractions in the equilibrium solutions were varied f… more
Date: August 10, 1962
Creator: Ames, L. L., Jr. & Knoll, K. C.
Partner: UNT Libraries Government Documents Department
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TWO AUXILIARY CODES FOR USE WITH RENUPAK

Description: Two IBM-7090 codes were written to aid the user of the neutron moments method code RENUPAK. One code computes and punches response function input cards for RENUPAK or NIOBE (another neutron transport code). The second code reads RENUPAK flux tapes and prints out a compact edit including dose rate as a function of distance. (auth)
Date: August 10, 1962
Creator: Trubey, D.K.
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program, A Boiling Water Reactor Research and Development Program Eighth Quarterly Progress Report April 1962 - June 1962

Description: The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors in several areas. This report presents updates on tasks related to those areas.
Date: July 10, 1962
Creator: Hodde, J. A.
Partner: UNT Libraries Government Documents Department
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