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909B high energy gull generator

Description: No Description Available.
Date: December 31, 1960
Creator: Stephens, W. H.
Partner: UNT Libraries Government Documents Department
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Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: January-March 1960

Description: Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: March 31, 1960
Partner: UNT Libraries Government Documents Department
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RADIOLOGICAL PHYSICS DIVISION SEMIANNUAL REPORT FOR JULY THROUGH DECEMBER 1959

Description: An investigation of the emission spectrum from radiation-daniaged xylene led to the conclusion that no gross corrections are needed for xylene when used as a scintillation solvent. Data are included from measurements of nonradioactive energy transfer in p-xylene and diphenyloxazole organic scintillation solutions. Measurements were made of the energy resolution of a twinscintillation fast neutron spectrometer. Accurate values of electron drift velocity in purified noble gases and nitrogen were obtained by measuring the transit time of photoelectrons across the gap of a parallel-plate condenser. Information concerning the transport collision cross section of low-energy electrons on noble gases was obtained from drift-velocity data. A method is discussed for the determination of traces of Freon-12 by positive ion emission techniques. Data are reported from late observations of the distribution of radium in the human body; the microscopic distribution of the dose in the skeleton arising from deposited calcium-45, strontium90, and radium-226 as measured autoradiographically; and determinations of individual alpha emitters in mixtures of alpha emitters. Data are tabulated from measurements of gross fission product radioactivity in air samples and in samples of soils collected from August through November 1959. The soil and air fall-out data are discussed. Measurements were made of the total-body gamma ray spectra of 13 unexposed employees chosen as typical of the civilian population of the Chicago area. Measurements were also made of cesium-137 content and cesium-l37/potassium-40 ratios. Data are included from measurements of natural uranium in the lungs of a human. The status is reviewed of a project to study the conditions of persons formerly engaged as radium dial painters and of a project to study the condition of persons who received radium by intravenous administration 21 to 29 years previously. Results are included from a survey of the radioactivity of commercial photomultiplier tubes. The activity induced in …
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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THERMAL STRESS TESTING OF SM-2 FUEL ELEMENTS. Interim Technical Report for January 1, 1959 to January 1, 1960

Description: Thermal stress testing was performed on two fuel plates, one cut from a brazed SM-1 dummy fuel element and the other from a TIG Welded SM-2 reference element. The test specimens were subjected to transverse temperature differences of up to 200 deg F, and distortion and strain at various locations were measured. The effect of the thermal stress was to increase the amplitude of original distortions. Adddtional distortions due to thermal stress were proportional to temperature differential and to ripple length. Tensile stresses in the side plate sections were measured as approximately 10,000 psi at maximum reactor temperature difference. Individual weld loadings in shear were measured as 38 lb per weld. Results of the tests were considered inconclusive because of unrepresentative initial plate distortion. (M.C.G.)
Date: October 31, 1960
Creator: Christenson, J.A.
Partner: UNT Libraries Government Documents Department
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PROCEEDINGS OF THE CONFERENCE ON THE PHYSICS OF BREEDING, OCTOBER 19-21, 1959

Description: Abstracts were prepared on 26 of 28 papers presented at the Conference on the Physics of Breeding held at Argonne National Laboratory on October 19 to 21, 1959. (C.J.G.)
Date: October 31, 1960
Creator: Fischer, G; Kelber, C; Meneghetti, D; Persiani, P; Shaftman, D & Smith, A.B. eds.
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1960

Description: Chemical-Metalluaical Processing. A direct-cycle fuelreprocessing plant using pyrometallurgical procedures is being designed as part of the Experimental Breeder Reactor No. II project. The reduction of uranium oxide was investigated, using pure Mg and solntions of Mg in Zn and Cd. Cadinium solntions of U were shown to be stable in Types 405 and 410 stainless steel containers at temperatures up to 550 deg C. The liquid metal corrosion loop in which a U-Mg--Cd alloy is being circulated at 550 deg C has been in trouble-free operation for 3000 hrs. Recovery of Pu from Mg solution by distillation of Mg was demonstrated on 1-g Pu scale. The solubility of Th in liquid Cd was measured over the temperature range from 1.9 x 10/sup -3/ per cent at 348 deg C to 1.8 x 10/sup -2/ per cent at 658 deg C. The solubility of Mn in liquid Cd was found to range from 0.27% at 414 deg C to 1.43% at 661 deg C. The solubility of Ni in liquid Cd was measured. The partition of U between liquid Al and liquid Cd was studied as a function of U concentration. The reaction of Al with a liquid Cd solution containing U, Zr, and Ce was studied. The free energy of formation of the U--Pb intermetallic compound UPb/sup 3/ was measured between 374 and 846 deg C by means of a galvanic cell method. Magnetic susceptibility measurements on the intermetallic comPound CeCd/sub 11/ were made over a range of temperature from 4 to 295 deg K. Fuel Cycle Applications of Volatility and Fluidization Techniques. The Direct Fluorination Process is currently aimed toward the processing of the Zircaloyclad, UO/sub 2/ fuel typical of the Dresden Reactor. The direct fluorination of dense UO/sub 2/ pellets submerged in an inert fluidized medium was carried …
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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USE OF SILICON SURFACE-BARRIER COUNTERS IN FAST-NEUTRON DETECTION AND SPECTROSCOPY

Description: A neutron-sensitive semiconductor counter was constructed by depositing a thin layer of Li/sup 6/F between two silicon surface-barrier counters. Neutrons are detected by observing the alpha + T pair resulting from the Li/sup 6/(n, alpha )T reaction; pulses from the two counters are added, and the sum pulse is amplified and recorded on a multichannel analyzer. Since the sandwich geometry permits simultaneous detection of both reaction products, the magnitude of the resulting sum pulse is proportional to the energy of the incoming neutron. Pulse-height spectra from slow neutrons and monoenergetic fast neutrons. in the energy region 0.6 to 3.5 Mev, were recorded from two counters of this type; in both counters the sensitive area was about 0.7 cm/sup 2/, with a Li/sup 6/F layer of order 150 mu g/cm thick. In all cases. a well defined neutron peak was observed in the pulse-height spectrum. In a typical case the full width at half maximum of the fast-neutron peak was about 300 kev. Counters of this type are relatively insensitive to background effects, notably gamma rays, and thus may prove to be useful in the detection and spectroscopy of fast neutrons. (auth)
Date: May 31, 1960
Creator: Love, T A & Murray, R B
Partner: UNT Libraries Government Documents Department
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An Improved Nuclear Density Gauge. Quarterly Report No. 2 Covering Period September 1 to December 1, 1959

Description: Techniques for improving stability of scintillation counter chopper systems and their development for use in industrial control applications are being investigated. Tests are being performed to determine the causes of fluctuations. An integration and frequency converter is being developed in which the anode current of the photomultiplier tube is alternately switched between two integrating condensers by action of a commutator switch. The voltages developed across the two condensers are proportional to the respective intensities of the two radiation beams seen by the scintillation counter. Slective sampling by the use of Loss filters is scheduled for future investigations and a literature search on counter stabilization is also planned. (J.R.D.)
Date: October 31, 1960
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
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METALLURGY DIVISION SEMIANNUAL PROGRESS REPORT FOR PERIOD ENDING OCTOBER 10, 1956

Description: Progress is reported in corrosion studies of stainless steels, Nb, Zr, Al- Fe-Mo, Mo, Ni alloys, and Al- Ni by various materials including Na, Na-K, Li, Rb, and fused salts, Corrosion studies in pump loops of various materials by fused salts and liquid metals are reported, Fuel elements and shielding materials for ART and APPR are beirg developed. General studies in welding and brazing, nondestructive testing, fabrication, and inspection are described. Developments in high-temperature metals and ceramics, metallographic techniques, ceramic materials, and Zr alloys are reported, (T.R.H.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT FOR JULY 1, 1959- SEPTEMBER 30, 1959

Description: ABS>Fuel Element Research and Development. Dynamic and static corrosion tests on 8001 Al were completed. Annealmmmg of 1100 cladding on 5083 and M400 cladding on X2219 were tested at 500 deg C, and investigation continued on producing X8101 Al alloy cladding in tube plates by extrusion. Boiler fuel element capsule irradiation tests and subassembly tests are described Heat transfer loop studies and fuel fabrication for the critical facility are reported. Boiler fuel element mechanical design and testing progress is desc ribed. and the superheater fuel element temperature evaluating routine is discussed. Low- enrichment superheater fuel element development included design studies and stainless steel powder and UO/sub 2/ powder fabrication studies Reactor Mechanical Studies. Research is reported on vessel and structure design, fabrication, and testing, recirculation system design, steam separator tests, and control rod studies. Nuclear Analysis. Reactor physics studies are reported on nuclear constants, baffle plate analysis, comparison of core representations, delayed neutron fraction. and shielding analysis of the reactor building. Reactor and system dynamics and critical experiments were also studied. Chemistry. Progress is reported on recombiner. radioactive gas removal and storage, ion exchanger and radiochemical processing. (For preceding period see ACNP-5915.) (T.R.H.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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DMM: A MULTIGROUP, MULTIREGION ONE-SPACE-DIMENSIONAL COMPUTER PROGRAM USING NEUTRON DIFFUSION THEORY. PART II. DMM PROGRAM DESCRIPTION

Description: Operating instructions are presented for DMM, a Remington Rand 1103A program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Complete descriptions of the routines and problem input and output specifications are also included. (D.L.C.)
Date: December 31, 1960
Creator: Kavanagh, D.L.; Antchagno, M.J. & Egawa, E.K.
Partner: UNT Libraries Government Documents Department
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AN IMPROVED NUCLEAR DENSITY GAUGE. Period covered: September 2 to October 1, 1959

Description: Progress in development of a nuclear density gage for use in thickness and density measurements is reported. A Ross filter system for energy discrimination in the alpha ray region was constructed. Soller slits for collimating the radiation entering and leaving the filters so that a constant absorber thickness is seen by the radiation beam is under construction. Comments by visiting Russian scientists on the density gage and a discussion of their work in this area are included. (J.R.D.)
Date: October 31, 1960
Creator: Burgwald, G.M.
Partner: UNT Libraries Government Documents Department
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Applied Mathematics Division Summary Report for July 1, 1959 Through June 30, 1960

Description: A summary of each computer program initiated during the report period together with code symbols indicating the extent to which information concerning the program is readily available are given. Programs previously reported are included if changes were made or additional information concerning them was placed in the program library. Abstracts of 704 newsletters and GEORGE bulletins are presented. (For preceding period see ANL-6089.) (W.D.M.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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Fuel Element Catastrophe Studies Hazards of Fission Product Release From Irradiated Uranium

Description: The rate of reaction of highly irradiated U with air, CO/sub 2/, and steam was studied in sn investigation of the fission product release potential in a loss-of-coolant type accident postulated for Pu-producing reactors. Highly irradiated U was found to be more reactive, probably because of the defects in the oxide coating formed by the inclusion of fission products. Complete oxidation or melting was found to release rare gases, I, and Te semi- quantitatively in most atmospheres. Other fission products (Ru, Cs, and Sr) were released to a lesser extent and apparently in proportion to the amount of self- heating induced. In order of their relative tendency to release fission products, the atmospheric conditions investigated were rated in the order: air > CO/sub 2/ > steam. (auth)
Date: October 31, 1960
Creator: Parker, G. W.; Creek, G. E.; Martin, W. J. & Barton, C. J.
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, AND MARCH 1957

Description: Fluoride Volatilization Separations Process. Development of a fused fluoride process for dissolution of uranium-- zirconium fuel alloys continued. In corrosion tests to find a suitable container material, Ni was found to be susceptible to a sulfur-type attack. Hastelloy B showed promise, and graphite offers excellent chemical resistance but poor mechanical strength. The dissolution rate of Zr in NaF-- ZrF as affected by impingement of the HF sparge was studied. Production of UF/sub 6/ by fluidized bed fluorination of UF/sub 4/ from ore concentrates was studied. The preparation, melting point, vapor pressure, and vapor density of UF/sub 5/ are given. Preliminary dissolution and recovery runs in semi-works equipment are discussed. Fluidization. Fluidized- bed techniques have been applied to conversion of UO/sub 2/(NO/sub 3/)/sub 2/ to UF/sub 4/ and to calcination of radioactive liquid wastes. Activities of the Green Salt Pilot Plant and shakedown runs of the shielded waste calciner are described. Reactor Chemistry. Studies continued on the kinetics and mechanism of oxidation of U, Th, and Zr. Data are given for oxidation of U in oxygen from 125 to 295 tained C and 20 to 800 mm pressure, and for Zr from 400 to 900 tained C and 200 nan O/sub 2/ pressure. The ratio of capture to fission cross sections for U/sup 233/ and U/sup 238/ in EBR-I have been determined as a function of position. ChemicalMetallurgical Separations Processes. Development of pyrometullurgical processing of spent reactor fuels continued. Work is repcrted on: melt refining and casting of U--Pu; iodine volatility problem; the system U--B-- Ta; the distribution coefficients for Pu between U--Cr and Mg and U and Mg; extraction of Pu from U by liquid Mg; Ce removal by dross refining; adsorption of volatilized metuls on surface active materials; and fractional crystallization of U with Zn. Analytical Research. A study …
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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