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State of Matter at High Pressure

Description: Abstract. The region where exact thermodynamic description of the state of matter at high pressure and high temperature is possible is located. In the remaining region various approximate theories and empirical relations are discussed. These considerations are applied to hydrogen to locate the density and pressure at which the diatomic bond collapses. Also the approximate conditions are determined at which no bound electron states exist.
Date: March 31, 1960
Creator: Alder, Berni J.
Partner: UNT Libraries Government Documents Department
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METALLURGY DIVISION QUARTERLY PROGRESS REPORT FOR PERIOD ENDING OCTOBER 31, 1952

Description: Physieal Metallurgy. In the study of Th alloys, it has been found that the addition of Nb and V to Th produces a slight strengthening effect with the first small additions, but that large additions result in a lowering of strength with corresponding increases in ductility. The melting point of iodide Th was measured as being 1755 deg C. Studies of a series of Th--C alloys, with C content up to 0.13%, indicate that C does not affect the temperatures for the start and completion of recrystallization. ANP Program. Welding specifications were prepared for the joining of Inconel pipe dan fitting. for use with highly corrosive media. The production of spherical particles of alloys of U with Ni, V, Nb, and Mo is being studied. The effect of small differences in test temperature in the stress-rupture life and creep rate of Inconel was studied. The effect of different cleaning procedures on the corrosive action of the fluorides on Inconel is being studied. Additional static and dynamic tests were run in an attempt to find inhibitors for the mass transfer and corrosion exhibited in the metal-hydroxide systems. The study of the compounds formed by the interaction of Ni in the hydroxides has shown the appearance of two new compounds: NaNiO/sub 2/ and LiNiO/sub 2/. Ceramics Research. A ceramic coating was successfully applied to Ni, and a Ni radiator assembly is being coated for the ANP Project. A technique for the synthesis of hafnium carbide was developed. Fabrication Research. Production of enriched U fuel and control red elements for operation of the MTR is described. (W.L.H.)
Date: October 31, 1960
Creator: Bridges, W.H. ed.
Partner: UNT Libraries Government Documents Department
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Weapons Effects for Protective Design

Description: A lecture intended to provide a general background in weapons effects is presented. Specific areas of nuclear explosion phenomena pertinent to the design of hardened systems discussed include nuclear radiation and shielding, fireball growth and effects, thermal radiation, air blast, cratering and throwout, ground shock effects, fallout, and afterwinds. (J.R.D.)
Date: March 31, 1960
Creator: Brode, H. L.
Partner: UNT Libraries Government Documents Department
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An Improved Nuclear Density Gauge Progress Report: October 1959

Description: Progress is reported on development of a scintillation detector which alternately views the radiation transmitted through a sample and through a calibrated wedge. From this information density and thickness data can be obtained. Long term stability measurements are being made on the commutating system and the causes of fluctuations are being investigated. Information concerning procurement and fund expenditure are given. (J.R.D.)
Date: October 31, 1960
Creator: Burgwald, G. M.
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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MAGNETIC RECORDER FOR NUCLEAR PULSE APPLICATION. Covering Period: August 6, 1959 to October 5, 1959

Description: Direct recording of nuclear pulse height data on magnetic tape is being investigated. The characteristics of various brands of commercial tape are being investigated and a waveform analysis is being performed in an attempt to determine the most favorable frequency range for available tapes. Use of the magnetic modulator head is being investigated to minimize variations due to short term tape speed variations. (W.L.H.)
Date: October 31, 1960
Creator: Burgwald, G. M. & Stone, C. A.
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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Sub-Cooled Burnout Relative to Hanford Reactors

Description: In the Hanford production reactors, failure of fuel element cladding is known as subcooled burnout since the bulk coolant temperature is below the saturation temperature at time of failure or burnout of the fuel cladding. The heat generation rate at which subcooled burnout occurs, establishes a limit to allowable reactor power level. This document compares present and potential power level limits at the Hanford production reactors with power level limits established by subcooled burnout.
Date: May 31, 1960
Creator: Carlson, P. A. & Trumble, R. E.
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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Progress Relating to Civilian Applications During January, February, March 1957

Description: These three reports were issued separately, but are cataloged as a unit. Progress is reported in the development of U and Zr alloys for Hanford Reactors, extrusion of Al-clad fuel plates, properties of UO/sub 2/, corrosion of stainless steels, salt baths for U heat treatment, galling in Mg-UF/sub 4/ compacting, development of U alloys for fuels, corrosion of U, development and testing of U- Zr alloys, corrosion of Zr and Zr alloys, constitution of ternary U alloys, corrosion problems in Zircex Process and Darex Prccess, and evaluation of a reflector-controlled heterogeneous boiling reactor. (For preceding period see BMI-1152.) (T.R.H.)
Date: October 31, 1960
Creator: Dayton, R. W. & Tipton Jr., C. R.
Partner: UNT Libraries Government Documents Department
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The Energy Gap in Nuclear Matter

Description: The magnitude of the energy gap in nuclear matter associated with a highly correlated ground state of the type believed to be important in the theory of superconductivity has been evaluated theoretically. The integral equation of Cooper, Mills, and Sessler is linearized and transformed into a form suitable for numerical solution. The energy gap, calculated by using an appropriate single-particle potential and the Gammel-Thaler two-body potential, is found to be a very strong function of the density of nuclear matter, and of the effective mass at the Fermi surface. It is concluded that the magnitude of the energy gap for nuclear matter should not be compared directly with experimental values for finite nuclei, although the results suggest that if the theory is extended to apply to finite nuclei it probably would be in agreement with experiment.
Date: January 31, 1960
Creator: Emery, V. J. & Sessler, A. M.
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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ISOTOPIC METHOD FOR AGE DETERMINATION OF INDUSTRIAL PRODUCTS. Quarterly Progress Report, July-September 1959

Description: >The materials and methods used for the long-term nuclide pairs are essentially the same as those previously described. (April - June Report). The split planchet method was used to determine the resolving time of the tracerlab superscalar counting apparatus which is currently in use. A planchet was split in two and a sample of nuclide placed in each half and counted. From these results a formula for calculating true counting rates was evolved. Data on resolving time loss for the Superscalar are tabulated. Transmission values of Sr/ sup 89/- Ct/sup 14/ mixture were measured to determine the degree to which error in these values can be reduced by long counting periods. Data on P/sup 32/ and C/ sup 14/ tagged rubber age counts are tabulated. Also, rubber samples were prepared by adding Ca/sup 45/, Cl/sup 36/, Nb/sup 95/, and T c/sup 99/, mixing and vulcanizing and isotope pairs (Ca/sup 45/- Cl/sup 36/ and Nb/sup 99/-Tc/sup 99/) were similarly incorporated in other samples. Ground and suspended samples of these preparations were age counted. The results obtained by incorporating radioisotopes into rubber can not show close correlation between observed and calculated time. Probable reasons for errors and inconsistencies are discussed along with plans for future work. (J.R.D.)
Date: October 31, 1960
Creator: Gregson, T.C. & Waisbrot, S.W.
Partner: UNT Libraries Government Documents Department
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Winchester Laboratory Quarterly Report: January 1, 1960-March 31, 1960

Description: Three methods for the determination of radium were evaluated. In two methods, the radium is finally precipitated with barium sulfate as carrier and alpha-counted. In the other method, the radium is recovered in a carrierfree condition for alpha counting. A method for determining radium by removing interfering elements with solvent extraction technniques and precipitating the radium with barium sulfate is described. A method which gives a rapid estimation of radium isotopic composition in samples, based on precipitation with barium sulfate, conversion to the carbonate, and alpha counting, is described. Flowsheets are contained on all five processes discussed. Two processes for the determination of thorium were evaluated. One method consists essentially of extraction of carrierfree thorium in TTA-benzene, stripped in nitric acid, and direct plating of the nitric acid solution for counting. The second method consists of thorium precipitation on lanthanum hydroxide, then on lanthanum fluoride, dissolution in nitric acid aluminum nitrate, thorium extraction into TTA solution, stripping into nitric acid, and counting. Flowsheets for the processes are given. The effects of pH, sulfate ion concentration, calcium and other contaminants, and temperature on the adsorption of radium from acid leach liquors by barite were studied. Coprecipitation studies of radium with barium sulfate from mill effluent streams were investigated. (For preceding period see WlN-115.) (C.J.G.)
Date: October 31, 1960
Creator: Herrington, A. C.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-344-A-FP, determination of the limitations of the Al-Si process

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can bond separation following irradiation. Such evidence has aroused concern for the ability of the currently produced Al-Si bonded fuel elements to withstand future reactor operating conditions. Several potential uranium fabrication and canning process improvements are being developed to further advance fuel element stability and performance. Optimization of process conditions based on these improvements may provide the necessary margin of safety for good bond layer integrity. Before a decision can be made to continue improvement of the present process or convert to a new canning process, more information on the stability of the present fuel element bond is needed. This report presents the design of a test to more fully evaluate Al-Si bond integrity under anticipated future reactor operating conditions.
Date: August 31, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
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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DMM: A Multigroup, Multiregion, One-Space-Dimensional Computer Program Using Neutron Diffusion Theory. Part 1 - The Theory

Description: DMM is a program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Calculations of fission-produced xenon and samarium and time variation due to production and depletion of isotopes are an essential part of this program. The adjoint fluxes may also be computed, and the program includes the calculation of the nuclear constaants from fairly simple input combined with a library of cross sections. The present code is written for the Remington Rand 1103A. Operating instructions are presented in Part II. (auth)
Date: December 31, 1960
Creator: Leshan, Edward J. & Kavanagh, Deveroux L.
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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