1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES (open access)

1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES

The computer program 1559/RE is an experimental IBM-704 code in FORTRAN language for computing the resonance integrals of isotopes in mixtures in the presence of hydrogenic moderation. There may be up to four isotopes, each with no more than 75 resolved resonance levels. Doppler broadening and interference scattering are included No estimate is made of contributions from unresolved resonances. Typical running times are 30 min (with no Doppler broadening) to 90 min (with Doppler broadening) for problems involving 67 levels and unit lethargy widths. Input and theory are discussed, and a typical listing is given. (auth)
Date: May 1, 1963
Creator: Kelber, C.N.
Object Type: Report
System: The UNT Digital Library
Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963 (open access)

Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963

Declassified 4 Sep 1973. A hot-working device for compression of graphite bodies was used to deform cylindrical specimens of matrix graphite containing ZrC or UC-ZrC particles to strains of the order of 30% at temperatures of 2400 to 2900 deg C. The graphite bodies containing ZrC particles (chosen as representative carbide particles) were found to be more plastic near 2500 deg C than similar bodies containing no carbide particles. Microradiographic techniques were used to determine diffusion coefficients of U and Th on actual coated particles by nondestructive means. A tentative energy of activation for the migration of uranium from UC/sub 2/ particles into PyC coatings was determined over the temperature range 1850 to 2300 deg C. The penetration of U into the coatings is not uniform but occurs radially in localized positions, and then spreads circumferentially, creating a banded structure. These results show the importance of the structure of PyC in regard to the diffusion of both fuel and fission-product materials. It was also observed that the diffusion of U is considerably more rapid in the direction parallel to the layer planes in the PyC than it is in the perpendicular direction. Tests with PyC-coated (U, Zr)C particles in graphite-matrix …
Date: May 1, 1963
Creator: Goeddel, W.V.; Sandefur, N.L. & White, J.L.
Object Type: Report
System: The UNT Digital Library
Analysis of LASL Core Bundling Pressure Test (open access)

Analysis of LASL Core Bundling Pressure Test

This is an analysis, based on a test conducted by LASL personnel, to determine whether relative expansion of two pieces of graphite under bundling loads would result in failure of the graphite.
Date: May 1, 1963
Creator: Brussalis, William
Object Type: Report
System: The UNT Digital Library
Assembly procedures, phase I vibration (core--inner reflector) (open access)

Assembly procedures, phase I vibration (core--inner reflector)

This document describes procedures to be followed and the equipment necessary to perform the assembly of the phase 1 vibration Core and the Inner Reflector. It contains the sequence of operations and identifies additional documentation and supplementary information.
Date: May 1, 1963
Creator: Zwillich, A.
Object Type: Report
System: The UNT Digital Library
BASIC MATERIAL RESULTING FROM ANL ROCKET STUDY (open access)

BASIC MATERIAL RESULTING FROM ANL ROCKET STUDY

The design and development of rocket reactors are considered. Topics included are: thermodynamic calculations of vapor pressure of uranium dioxide, uranium xeonosulfide, uranium monocarbide, zirconium monocarbide, beryllia, and tungsten; thermodynamic calculations of equilibrium interactions of the above materials with hydrogen or water; verification of muitigroup constants used in reactor physics calculations; relations pertaining to a heat transfer parameter study; a heat transfer coefficient correlation for hydrogen; a FORTRAN-II subroutine to compute thermal properties of hydrogen; considerations pertaining to reactor control; and fuel plate stress analyses. (N.W.R.)
Date: May 1, 1963
Creator: Cohn, C.; Golden, G.; Hoglund, B.; Loewenstein, W.; Rosenberg, G.; Sparks, D. et al.
Object Type: Report
System: The UNT Digital Library
Beryllium Reflector Specimen Thread Strength Tests (open access)

Beryllium Reflector Specimen Thread Strength Tests

Strengths at failure are reported for a number of threaded beryllium specimens loaded in tension at room temperature and -320 degrees F. Loads greater than normal bolt strengths were repeatedly carried. The standard fine thread was somewhat stronger than the standard coarse thread. Material at the entrance of the hole should be counter-bored about one diameter deep in order to resist cone-type fracture. Pure tensile loading should be used. Possible shear loading should be carried by separate pins to avoid bending moments, since this effect has not yet been evaluated. Two diameters of thread engagement is sufficient for strength; greater engagement has no advantage.
Date: May 1, 1963
Creator: Kallin, I. N.
Object Type: Report
System: The UNT Digital Library
BIOLOGICAL AND MEDICAL RESEARCH DIVISION SEMIANNUAL REPORT, JANUARY THROUGH JUNE 1962 (open access)

BIOLOGICAL AND MEDICAL RESEARCH DIVISION SEMIANNUAL REPORT, JANUARY THROUGH JUNE 1962

None
Date: May 1, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
CARBIDE FUEL DEVELOPMENT. Progress Report, October 1, 1962-March 31, 1963 (open access)

CARBIDE FUEL DEVELOPMENT. Progress Report, October 1, 1962-March 31, 1963

FUEL FABRlCATlON AND EVALUATION. The synthesis and fabrication of (UO/ sub 0.95/Pu/sub 0.05/)C/sub 0.98/ test specimens by cold pressing and sintering for out-of-pile property measurements were completed. Theoretical densities of 91% (avg) were obtained without sirtering aid and 96% (avg) with 0.1 wt% nickel sintering aid. Mixed sesquicarbide, ated into pellets 94% of theoretical density. Massive, carbon-stabilized PuO was synthesized by the carbon reduction of the dioxide. The carbon content of the product was 0.14 wt%. The coefficients of expansion of (U/sub 0.95/Pu/sub 0.05/)C/sub 0.098/ with and without nickel sintering aid were measured to 1400 deg C, and found to be 12.2 to 12.6 x 10/sup - 6/DEC. Measurements of melting point and vapor pressure of mixed monocarbides were started by testing standards. Compatibility tests at 593 and 816 deg C were started. Examinarion of results to date show a reaction between (U/sub 0.95/Pu/ sub 0.05/)C/sub 0.98/ and Zircaloy-2, and no reaction with type 316 stainless steel and niobium after 1000 hr at 816 deg C. This is similar to previous results with UC. IRRADIATION TESTS. The assembly of all the irradiation capsules was completed. Ten of the 12 planned specimens of (U/sub 0.8/Pu/sub 0.2/) C/sub 0.95/ are currently operating …
Date: May 1, 1963
Creator: Strasser, A.; Stahl, D.; Taylor, K. & Anderson, J.
Object Type: Report
System: The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, OCTOBER-DECEMBER 1962 (open access)

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, OCTOBER-DECEMBER 1962

Summaries are presented of research developments in: chemical- metallurgical processing studies in pyrometallurgy, fuel-processing facilities for EBR-H, and the chemistry of liquid metals; fuel-cycle applications of volatility fluidization techniques to laboratory- and engineering-scale investigations of fluoride volatility processes, and the conversion of UF/sup 6/ to UO/sup 2/; calorimetry studies of the combustion of metals in fluorine, and the development of a high-temperature enthalpy calorimeter,; reactor safety evaluations of metal oxidation and ignition kinetics, and metal-- water reactions; energy-conversion studies of regenerative emf cells, and thermoelectricity; the determination of nuclear constants for double neutron capture experiments, and capture and fission reactions in EBR-II; and routine operations in waste processing and in the high-level gamma-irradiation facility. (B.O.G.)
Date: May 1, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Completion Report for Contracts AT(10-1)-1054, AT(10-1)-1122 : Drilling, Casing and Cementing Observation Wells at the National Reactor Testing Station, Idaho (open access)

Completion Report for Contracts AT(10-1)-1054, AT(10-1)-1122 : Drilling, Casing and Cementing Observation Wells at the National Reactor Testing Station, Idaho

Report that "summarizes the costs, experience and results of contracts AT(10-1)-1054 and AT(10-1)-1122 for drilling, casing and cementing observation wells at the National Reactor Testing Station, Idaho" (p. [11]).
Date: May 1, 1963
Creator: Keys, W. S.
Object Type: Report
System: The UNT Digital Library
Condensing Flow in Finned, Tapered Tubes (open access)

Condensing Flow in Finned, Tapered Tubes

On the assumption that a Lockhart-Martinelli type of correlation is applicable, an analytical approach to the interpretation of pressure drop data on condensing flow in tapered tubes was developed with particular reference to the condensation of potassium in a radiant condenser of a type that may be attractive for space power plants. It appears that instability can be encountered in such condensers only through the introduction of excess liquid inventory at reduced power or by design of the condenser for insufficient pressure drop at design power. (auth)
Date: May 1, 1963
Creator: Korsmeyer, R.B.
Object Type: Report
System: The UNT Digital Library
Conditional Monte Carlo Program for Solving the Transport Equation (open access)

Conditional Monte Carlo Program for Solving the Transport Equation

This report has been prepared primarily for internal use. The computer program it describes is presently being revised as outlined in Section V of Part I. The lessons learned from experience on proper source mesh spacing, choice of conditional weight function, ect. are not discussed in this report. Use of the program to compute eigenvalues is only outlined. The latter will be discussed in a subsequent report.
Date: May 1, 1963
Creator: Killinger, A.H.; Saalbach, C.P. & Drawbaugh, D.W.
Object Type: Report
System: The UNT Digital Library
Conference on Clean Room Specifications (open access)

Conference on Clean Room Specifications

This report addresses the conference on clean room specifications held at Sandia Laboratory Albuquerque, New Mexico during April 9 and 10, 1963.
Date: May 1, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
THE CONVERSION OF ELECTROMAGNETIC ENERGY INTO SHOCK PULSES (open access)

THE CONVERSION OF ELECTROMAGNETIC ENERGY INTO SHOCK PULSES

The repulsion-coil technique for energy conversion offers a powerful, new tool in the field of acculeration testing. Using this technique, a prototype magnetic shock device was developed that uses electrical energy stored in a capacitor bank to produce high-g, mechanical acceleration pulses. A disc projectile is vacuum-held against the core of an electromagnet coil, and a crystal accelerometer is attached to the projectile to monitor the pulse. The capacitor bank is charged to a specific voltage between one and 20 kv, then discharged into the coil. The resultant magnetic field around the coil effects a repulsion of the projectile, which is mechanically free to move away from the coil. By varying the capacitor voltage, the magnitude of the pulse can be predicted and controlled. The application of electrical-energy conversion in the production of a controllable acceleration pulse toward development of a magnetic shock device for component testing and instrument calibration is demonstrated. (auth)
Date: May 1, 1963
Creator: Meagher, T.F.
Object Type: Report
System: The UNT Digital Library
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment (open access)

Corrosion Studies in Simulated N-Reactor Secondary System Water Environment

Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Date: May 1963
Creator: Larrick, A. P.
Object Type: Report
System: The UNT Digital Library
The Cross Section, Volume 9, Number 12, May 1963 (open access)

The Cross Section, Volume 9, Number 12, May 1963

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.
Date: May 1963
Creator: High Plains Underground Water Conservation District No. 1 (Tex.)
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
The Crystal Structure and Hydrogen Bonding of Magnesium Sulfate Hexahydrate (open access)

The Crystal Structure and Hydrogen Bonding of Magnesium Sulfate Hexahydrate

None
Date: May 1, 1963
Creator: Zalkin, A.; Ruben, H. & Templeton, D. H.
Object Type: Report
System: The UNT Digital Library
DESIGN AND OPERATION OF FORCED-CIRCULATION CORROSION TESTING LOOPS WITH MOLTEN SALT (open access)

DESIGN AND OPERATION OF FORCED-CIRCULATION CORROSION TESTING LOOPS WITH MOLTEN SALT

Standardized test facilities were developed and operate for investigating the compatibility of structural materials and flowing molten fluoride salts. The standard loop accommodates various combinations of materials, fluid, flow, rates, and temperature differentials and permits fabrication of components in sufficient quantity for cost reduction. The test loop consists of a pump, two heated sections, a cooled section, a drain tank, and a frozen-plug-type valve. Automatic controls and equipment were developed to prevent solidification of the salt mixtures (mp, 800 to 1100 un. Concent 85% F) in the event of a loss of power. Most test loops were fabricated of 0.5-in.-OD, 0.045-in.-wall tubing, and operate with a temperature differential of up to 200 un. Concent 85% F, a maximum wall temperature in the range 1200 to 1500 un. Concent 85% F, and a salt flow rate of up to 3 gpm. Twenty-five test loops were operated for an accumulated operating time of 290,00 hr. Individual loops were operated continuously for more than one year. (auth)
Date: May 1, 1963
Creator: Crowley, J. L.; McDonald, W. B. & Clark, D. L.
Object Type: Report
System: The UNT Digital Library
DEVELOPMENT AND EVALUATION OF PROTOTYPE REMOTE-CONTROLLED SODIUM-BONDING AND BOND-INSPECTION PROCESSES FOR EBR-II FUEL CYCLE FACILITY (open access)

DEVELOPMENT AND EVALUATION OF PROTOTYPE REMOTE-CONTROLLED SODIUM-BONDING AND BOND-INSPECTION PROCESSES FOR EBR-II FUEL CYCLE FACILITY

The EBR-II plant includes an integral, remote-controlled Fuel Cycle Facility wherein spent fuel elements are to be pyrometallurgically refined, refabricated, inspected, and reassembled for return to the reactor. A description is given of the experimentally supported changes and refinements made in the prototype sodium-bonding and bondinspection equipment to ensure: (1) acceptable fuel elements for the initial core loading; and (2) equally acceptable elements in production quantities in the parent installation. More specifically, the mode of imparting bonding energy to the fuel element was changed from a vibratory action to a series of timed impacts. This reflected an increase in the yield of acceptable elements and a reduction of machine operation time. A nondestructive, eddy-current instrument was developed and demonstrated as capable of detecting all defects in the liquid sodium bond. The diameter of the lower restrainer knob in the fuel element was increased to eliminate eccentricity as a contributor to erratic level of the sodium bond. As a result, the sodium level can be detected to a tolerance of plus or minus /1/64 in. with a single, encircling eddy-current coil. Shrinkage voids in the sodium were not encountered. However, laboratory test data are presented in support of the conclusions that: …
Date: May 1, 1963
Creator: Cameron, T.C. & McCall, H.M. Jr.
Object Type: Report
System: The UNT Digital Library
Dispersion-Strengthened Vanadium Alloys. Bimonthly Report No. 2, February 14, 1963-April 13, 1963 (open access)

Dispersion-Strengthened Vanadium Alloys. Bimonthly Report No. 2, February 14, 1963-April 13, 1963

Arc-melting and powder metallurgy techniques are being used to incorporate fine, refractory dispersants in V-- Nb base alloys in order to improve their long-time elevatedtemperature strength properties. Solution annealing and aging studies of arc-melted alloys containing Hf or Zr in combination with C indicate that the Hf carbide phase is the more stable. The hydride process was used to obtain powders of V-60 wt% Nb-1 wt% Ti, to which fine oxide or carbide powders were added. After blending, coldcompacting, sintering at 2800 l F, and annealing at 2000 and 2400 l F, specimens containing alumina and thoria exhibited a high degree of reactivity with the alloy base. Improved stability was noted in the alloys containing ceria, lanthana, yttria, Hf carbide, and Zr carbide. (auth)
Date: May 1, 1963
Creator: Holtz, F. C.
Object Type: Report
System: The UNT Digital Library
Economic Factors of MFP Thermoelectric Generators. Final Report (open access)

Economic Factors of MFP Thermoelectric Generators. Final Report

Economic aspects of power generation from underwater thermoelectric generators fueled with Mixed Fission Products (MFP) are given. Costs are estimated to be less than 15 per thermal watt for two year old MFP. Studies are on a conceptual design of a unit capable of withstanding pressures equivalent to 18,000 feet submergence on the ocean bottom and 300 year containment of the nuclear heat source. Low cost bioiogical shields of both high density concrete and cast iron were considered. Studies establish the possibility of power costs as low as per watt-year in the kilowatt size, to 0 per watt-year in the 10 watt range. A comparison of the MFP generator with an equivalent SNAP-7 strontium-90 type indicates that the MFP power costs are far below those for separated radioisotope power, primarily because the highest cost item in the SNAP unit is the purified strontium-90 fuel. A one kilowatt MFP unit would weigh in the order of 20 to 30 tons maximum depending on fuel energy density, and have a diameter of 8 to 10 feet. Optimization studies were made for such factors as fuel geometry, fuel age, energy density, and insulation thickness to determine the most productive areas of reducing the …
Date: May 1, 1963
Creator: Lemanski, E.J.
Object Type: Report
System: The UNT Digital Library
Electron Microscope Studies of Irradiated Beryllium Metal (open access)

Electron Microscope Studies of Irradiated Beryllium Metal

When beryllium is irradiated by fast neutrons, helium is produced by the (n,2n) and (n,α) transmutation reactions. Electron microscopy techniques have been used to study the nucleation and distribution of helium bubbles in several different grades of beryllium, after irradiation at temperatures in the range 75 — 700ºC. The effect of post-irradiation annealing is also reported. It is shown that for similar neutron doses and irradiation temperatures, there were wide variations in helium bubble size and distribution in specimens of beryllium fabricated by different methods. The most satisfactory material was that fabricated from Pechiney powder by direct hot extrusion followed by annealing for one hour at 800ºC and air cooling, it is suggested that the helium bubbles nucleate on second phase precipitates and that the distribution of this phase is strongly affected by fabrication and heat treatment.
Date: May 1963
Creator: Chute, J. H.
Object Type: Report
System: The UNT Digital Library
THE ELECTRON RADIOLYSIS OF BENZENE-M-TERPHENYL AND PERDEUTEROBENZENE-M- TERPHENYL MIXTURES (open access)

THE ELECTRON RADIOLYSIS OF BENZENE-M-TERPHENYL AND PERDEUTEROBENZENE-M- TERPHENYL MIXTURES

None
Date: May 1, 1963
Creator: Moffat, A. J.
Object Type: Report
System: The UNT Digital Library
Environmental Factors Affecting Ground Mobility in Thailand: Preliminary Survey, Appendix B: Soil Classification (open access)

Environmental Factors Affecting Ground Mobility in Thailand: Preliminary Survey, Appendix B: Soil Classification

"This appendix discusses the methods used to classify soils for the preliminary Thailand study and presents pedological soil profile descriptions" (p. B1).
Date: May 1963
Creator: Waterways Experiment Station (U.S.)
Object Type: Report
System: The UNT Digital Library