84 Matching Results

Search Results

Results: 1 - 24 next
open access

Investigation of impulsively loaded pressure vessels

Description: Explosion containment vessels for containing from 2,000 to 3,000 five ton nuclear explosions are considered. Analysis methods appear adequate and lowest weights using the most advanced materials available in the next five years are projected.None of these materials can be fabricated today and all require extensive development. Present material technology limits the choice of materials and defines the weight. The addition of safety factors and fixtures (nozzles, etc.) will add to this weight con… more
Date: October 15, 1963
Creator: Brown, N.; Cornwell, R.; Hanner, D.; Leichter, H. & Mohr, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

I. The Theory of Aberrations of Quadrupole Focusing Arrays. II. Ion Optical Design of High Quality Extracted Synchrotron Beams With Application to the Bevatron

Description: In Part One they formulate in a general way the problem of analyzing and evaluating the aberrations of quadrupole magnet beam systems, and of characterizing the shapes and other properties of the beam envelopes in the neighborhood of foci. They consider all aberrations, including those due to misalignments and faulty construction, through third order in small parameters, for quadrupole beam systems. One result of this study is the development of analytic and numerical techniques for treating th… more
Date: May 15, 1963
Creator: Meads, Philip Francis, Jr.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
open access

BETA RADIATION PROCESSING AT RIGOROUS CONDITIONS

Description: An investigation was conducted on the impossible use of beta radiation to promote chemical reactions at high temperatures and pressures. The advantages of beta sources over other radiation sources are enumerated. A radiation processing apparatus is described which allows operations to 10,000 psi and 500 deg C and uses 90 C of Sr/sup 90/-Y/sup 90/. The dosimetry of the source was accomplished with an iodineheptane system, and the mean dose rate within the chemical reactor was determined to be 0.… more
Date: November 15, 1963
Creator: Yavorsky, P M & Gorin, E
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

HEAT TRANSFER IN OSCILLATING FLOW. Aeronautical Engineering Report No. 483-e, June 30, 1963

Description: Pressure oscillations imposed upon a compressible fluid flowing in a duct produce a substandtial increase of heat transfer between the heated duct wall and the fluid. An experimental investigation was made of the causes of this increase. Resonant conditions in a duct were used to achieve increased oscillating amplitudes. The local heat transfer incresse was found to be highly dependent on the amplitude of the local velocity oscillations, and to depend also on the frequency of oscillations and t… more
Date: July 15, 1963
Creator: Marec, J. & Harrje, D.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CHARACTERISTICS OF A THERMIONIC CONVERTER WITH A HIGH-TEMPERATURE COLLECTOR

Description: Current-voltage characteristics of a cesium-on-tantalum thermionic converter with a collector temperature comparable to that of the emitter were obtained for a variety of electrode temperatures and cesium vapor pressures. The results show that for emitter temperatures in excess of 2000 deg K, power outputs of a few watts per square centimeter can be obtained when the ratio of collector temperature to emitter temperature is as high as 0.75 to 0.80, which is the required range for best performanc… more
Date: January 15, 1963
Creator: Blue, E. & Ingold, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRODUCTION OF STRONTIUM-TITANATE RADIOISOTOPE FUEL FOR SNAP 7B THERMOELECTRIC GENERATOR

Description: The conversion of strontium-90 to strontium titanate heat source pellets is described. Encapsulation of the fuel in Hastelloy C containers and necessary leak testing, decontamination and calorimetry procedures are covered. Loading of the SNAP 7B thermoelectric generator was accomplished. (auth)
Date: April 15, 1963
Creator: Bloom, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

KINETIC STUDIES OF HETEROGENEOUS WATER REACTORS. Quarterly Progress Report for Period Ending September 30, 1963

Description: Additional measurements were made of steam-void fraction, temperatures, and pressures in the KEWB capsule experiment. Analysis of data indicated that friction in the volume transducer piston was large during most of the transients. The dynamic piston friction was reduced to negligible magnitudes. A method for calculating the transient heat flux from the fuel disc was formulated. Boiling stability experiments were begun with a 2-ft-long rod bundle, consisting of a square array of 18 stainless-st… more
Date: October 15, 1963
Creator: Wentz, L.B. & Zivi, S.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LABORATORY DEVELOPMENT OF A COMBINED CHLORIDE VOLATILITY-AQUEOUS PROCESSING METHOD FOR URANIUM-ZIRCONIUM NUCLEAR FUELS

Description: The operations in a process proposed for recovering uranium from spent uranium-- zirconium alloy fuels, including collecting the volatilized chlorination products (mainiy zirconium tetrachioride and uranium pentachloride) in boiling water, concentrating the resulting solution, lowering the freezing point by removing chloride with hydrogen peroxide, and recovering uranium from the 5 M Zr product solution by solvent extraction with tributyl phosphate in Amsco diluent, were investigated in the lab… more
Date: October 15, 1963
Creator: Gens, T.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of salt velocity technique

Description: The salt velocity technique for measuring coolant flow through a SNAP 8 tri-cusp channel was studied and developed. The parameters important in obtaining reproducible data were investigated and a test procedure, which yields dath of good precision, was developed. Dath were taken on a tri-cusp channel with flush circular electrodes (0.125 inch O.D.) as well as on a tri-cusp channel with parallel plate electrodes (0.006 inches thick, 0.250 inches long), which were situated 0.050 inches apart and … more
Date: November 15, 1963
Creator: Daleas, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Magnesium-28-Aluminum-28 System: An Aluminum-28 Generator

Description: A milking method was developed for the production of the short-lived Al/ sup 28/ for use in physiological experiments. A Mg/sup 28/ solution is obtained by the irradiation and purification of a Li/sup 6/Mg/sup 26/ alloy, and it is placed on a Dowex 50W column in the Na/sup +/ form and then washed with 1 N NaOH. The Al/sup 28/ is eluted in 10 to 30 sec by 1 N NaOH solution containing 0.5 mg/ ml of carrier Al. The half lives of Mg/sup 28/ and Al/sup 28/ were determined to be 20.88 plus or minus 0… more
Date: March 15, 1963
Creator: Weiss, A. J. & Hillman, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

REACTOR DEVELOPMENT PROGRAM. Progress Report, November 1963

Description: Development progress is reported on fast reactors, liquid metal cooled reactors, ZPR-III, ZPR-VI, ZPR-IX, Borax-V, Faret, EBR-I, EBR-II, Treat, Fermi Fast Breeder Reactor, critical assemblies, Argonne Fast Source Reactor, EBWR, Argonne Advanced Research Reactor, magnetohydrodynamic cells, fuel cells, and boiling water reactors. Reactor technology is reported on fuel development and properties, physics, heat engineering, materials development, chemical separations, nuclear safety, and nondestruc… more
Date: December 15, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, OCTOBER 1963

Description: Research and development progress is reported on BORAX-V, fast-reactor physics, fast-reactor fuel, EBRII, FARET, applied nuclear physics, theoretical nuclear physics, reactor fuels, reactor materials, metallurgy alpha - gamma hot cell, heat engineering research, chemical separations, plutonium recycle program, magnetohydrodynamics, rocket fuel test reactor, nuclear safety, and TREAT. (M.C.G.)
Date: November 15, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SRE Systems and Components Experience. Core II

Description: The design and performance of SRE Core II fuel elements, moderator cans, hot traps, cold traps, control elements, pumps, main primary heat exchanger, valves and sodium piping, and instrumentation are discussed. (R.E.U.)
Date: November 15, 1963
Creator: Pearson, E. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

BREMSSTRAHLUNG IN A DENSE PLASMA

Description: The bremsstrahlung emitted by an electron scattered in a Coulomb field was first calculated by Bethe and Heitler. The total cross section for production of photons with wave number between k and k + dk by a nonrelativistic electron of kinetic energy {epsilon} is d{sigma}/dk dk = 16/3 Z{sup 2}r{sub 0}{sup 2} (e{sup 2}/hc) (mc{sup 2}/{epsilon})log ({radical} {epsilon}/hck + {radical} {epsilon}/hck -1) dk/k, where Ze is the charge of the (heavy) ion, and r{sub 0} is the classical electron radius. … more
Date: January 15, 1963
Creator: Stack, John D. & Sessler, Andrew M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Control Drum Actuator Checker

Description: The Control Drum Actuator Checker is used to verify the operation of the hydraulic control drum actuators before they are installed on the reactor. It provides for local checkout after installation. It provides for local checkout after installation. It also provides for pre-installation hydraulic leak and pneumatic seal test on individual actuator assemblies.
Date: November 15, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen