45 Matching Results

Search Results

Results: 1 - 24 next
open access

Determination of the Nil-Ductility-Transition Temperature for A212B Steel Used in the N. S. Savannah Pressure Vessel

Description: The nil-ductility-transition (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah nuclear reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness location from materials used in the upper closure head of the reactor vessel yielded NDT temperatures of 0 - 20°F which correspond to Charpy-V-notch impact energ… more
Date: July 23, 1959
Creator: Thurber, W. C. & Lamartine, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Rate of Uranium Sorption by a Strong-Base Anion-Exchange Resin

Description: The rate of uranium sorption by a strong-base anion-exchange resin (Dovex 21K) from a uranyl sulfate solution (U 0.005 M, H2SO4 0.02M, SO4 0.2 M) was studied using a stirred vessel technique and measuring the U235 gamma radiation on each bead. Resin initially in the chloride form and the sulfate for was studied.
Date: July 8, 1959
Creator: Bresee, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of Oxygen in Oxide Films by Neutron Activation Analysis

Description: Preliminary experiments have been conducted to evaluate the use of the nuclear reactions Li6 (n,α)H3 and O16(H13,n)F18 to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10^11 n/cm^2/sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F18 of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities ma… more
Date: July 15, 1959
Creator: Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of Li6 in Aqueous Solution by Neutron Activation Analysis

Description: A method for determining the concentration of Li6 in aqueous solution has been tested using the nuclear reactions Li6 (n,α)H3 and O16 (H3,n)F18. Annihilation 7 radiation of induced 1.87 hour F18 radioactivity was counted with a well-type scintillation counter, and the radioactivity per millimole of lithium was found to be independent of lithium concentration below about 0.2moles/liter. The sensitivity limit for detecting lithium is less than 0.1 micromole (0.0075 micromole Li6).
Date: July 10, 1959
Creator: Winchester, J. W. & Bate, L. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Time Dependence of the Beam in the 86-Inch Cyclotron

Description: In the preliminary stages of getting up a time-of-flight system for measuring neutron spectra from proton reactions, a study of the time dependence of the beam in the 86Inch Cyclotron was made. This study revealed the expected bunching of the protons to produce a short burst of beam on each cycle of the 13.4 Mc/s accelerating voltage. In addition to the 13.4 Mc/s structure, however, there was a 360 c/sec modulation of the beam pulses and a complicated pattern built upon that.
Date: July 29, 1959
Creator: Goodman, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigation of Mechanical Methods of Scale Removal from HRT Heat Exchangers

Description: Tests were conducted to determine methods of removing scale deposits from the HRT heat exchangers. A mockup of the heat exchanger header was cleared of a deposit of iron rust by reverse flushing at a flow rate below 75 gpm. A tube bundle consisting of 109 1/4in. O.D. x 0.049 in. wall tubes was plugged with rust. Approximately 80% of these tubes were unplugged by using a 70 psi water pressure differential in combination with vibration from a pneumatic rivet gun. No mechanical method was employe… more
Date: July 21, 1959
Creator: Gabbard, C. H.; Eissenberg, D. M.; Moyers, J. C. & Namba, I. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Parametric Study of a Gas Cooled Reactor

Description: The results of a parametric study on a gas cooled reactor are reported on herein. The system considered was a helium cooled, UO2 fueled arrangement with the fuel assemblies consisting of clusters of long cylindrical elements, each element covered b a stainless steel jacket. The axial power distribution was assumed to be a "chopped cosine" having an axial peak-to-average power 1.32.
Date: July 24, 1959
Creator: Epel, L. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRFR Pilot Leaching Plant - Preliminary Process Design

Description: The preliminary process design of a PRFR pilot leaching plant, which is proposed to be located in Cell B of Building ORNL, is considered. Chemical, physical, and nuclear parameters are investigated in order that the leaching operations may be carried out without any chemical or nuclear hazards.
Date: July 23, 1959
Creator: McLain, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Multiplication Measurements with Highly Enriched Uranium Metal Slabs

Description: A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. slabs of 93.4% U235-enirched uranium metal have been made to provide data from which safety criteria for the storage of these fissile units can be established. Each slab contained 22.9 kg of U235. A maximum of 125 unites was assembled. The arrays studied were cubic lattices of the units and were usually parallelepipedal in shape.
Date: July 27, 1959
Creator: Mihalczo, J. T. & Lynn, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Multigroup Diffusion Theory Calculations for Recent Critical Experiments

Description: In connection with the program of the measurement of eta for U233, several critical experiments have been performed by R. Gwin and D. W. Magnuson of ORML with light water solutions of uranyl nitrate (highly enriched in either U233 or U35) in an essentially bare sphere 27 inches in diameter. This report presents the results of two multigroup-diffusion-theory calculations for the above experiments performed by C. B. Mills and associated at Los Alamos. Assumer cross sections, material concentratio… more
Date: July 21, 1959
Creator: Nestor, C. W., Jr
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Run 300A-B Slurry Run of 300A Pump and Loop

Description: The 300A and loop were operated for 2862 hr with thorium oxide slurry at 1500 psi and 280ºC to determine the effects vane inlet and exit geometries on impeller wear, the wear rate of aluminum oxide bearings in this size pump, and the operating characteristics of the loop. The thoris, a 1600*C-fired oxide, had a mean particle size of approximately 2 u. Average circulating slurry concentration was approximately 450 grams of thorium per kilogram of water and average flow rate was approximately 300… more
Date: July 2, 1959
Creator: Moyers, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Test of Heater and Cooler Concepts for OCR-ORR Loop, Design 4

Description: High heat flux electrical cartridge heaters were tested with direct air cooling under simulated ORR Loop conditions. The cartridges and the heater design were found to be satisfactory. A gas cooled of concentric pipe design utilizing air, water, and air-water mixtures as the coolant was also evaluated and found to be satisfactory.
Date: July 13, 1959
Creator: Kelley, W. H., Jr. & Storto, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Eurochemic Assistance Program: Comments by FMPC, dated July 6, 1959, on Eurochemic Technical Documents

Description: The nuclear safety portion of this report is inclined to ignore the factors by which safety limits can be increased. It makes no mention of the control that can be exercised by limiting the assay of the U-235 being processed in the plant. From some of the previous reports, it is apparent that this plant is not anticipating processing U-235 of assay greater than approximately 20%. At this value, many of the numbers that are presented in the tables could be increased markedly. Rough examination i… more
Date: July 14, 1959
Creator: Cuthbert, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel

Description: The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000-1200°C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-… more
Date: July 31, 1959
Creator: Cherubini, Julian H. & Leitten, C. F., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analytical Chemistry Division Semiannual Progress Report for Period Ending April 20, 1954

Description: Progress report of the Oak Ridge National Laboratory Analytical Chemistry Division providing updates on various projects, experiments, and other work in ionic analyses, analytical instrumentation, radiochemical analyses, activation analyses, spectrochemical analyses, inorganic preparations, optical and electron microscopy.
Date: July 5, 1956
Creator: Kelley, M. T.; Susano, C. D. & Raaen, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fabrication of Heat Exchangers and Radiators for High Temperature Reactor Applications

Description: Two 500-kw fused-fluoride-to-Nak heat exchangers, two 500-kw NaK-to-air radiators, and a 20-tube high-velocity heat exchanger were fabricated for a heat-exchanger development program. A construction procedure, utilizing both inert-arc-welding and high temperature dry-hydrogen brazing, was used successfully on all of the units. The tube-to-header joints were welded and back-brazed; the manifold joints were inert-arc-welded with full penetration; and the tube-to-fin joints were brazed. A detailed… more
Date: July 5, 1955
Creator: Patriarca, P; Slaughter, G. M.; Manly, W. D.; Heestand, R. L.; Clausing, R. K.; Conner, O. K. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report For Period Ending June 10, 1955

Description: The development of the reactor layout is continuing. New features that have been incorporated because of stress, fluid flow, or fabricability considerations include an elliptical fuel expansion tank, a rounded dome to enclose the top of the reactor, a newly designed sodium pump impeller, and other related items. Recently completed heat exchanger tests yielded consistent data from which a series of heat exchangers is being designed. The most promising of these will be chosen for the ART.
Date: July 28, 1955
Creator: Jordan, W. H.; Cromer, S. J.; Strough, R. I.; Miller, A. J. & Savolainen, A. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Homogenous Reactor Project Quarterly Progress Report For Period Ending April 30, 1955

Description: Part I. Experimental Reactors: The effect of prompt-neutron lifetime upon reactor safety was investigated for the HRT. It was found that for a given pressure rise the allowable rate of reactivity addition was relatively insensitive to the average prompt-neutron lifetime, although the rate de creased somewhat with decreasing lifetime for the higher pressure rises. With only source neutrons present and the reactor initially subcritical, the allowable rate was practically independent of the initia… more
Date: July 14, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Diffusion of Ions in a Plasma Across a Magnetic Field

Description: A theoretical and experimental investigation of the coefficient for diffusion of ions across a magnetic field Is described. The resultant diffusion coefficient is found to vary inversely as the square of the magnetic field strength, in accord with the usual collison-diffusion theory. The magnitude of the coefficient is much larger (x700) than the coefficient predicted by the usual ambipolar diffusion theory. This discrepancy is resolved by showing that diffusion across a magnetic field is not a… more
Date: July 1955
Creator: Simon, Albert & Neidign, Rodger V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of Plutonium and Uranium in Scrup Dissolver Solutions

Description: Methods for the determination of plutonium and uranium in highly radioactive scrup dissolver solutions have been developed. Plutonium was separated from the dissolver solutions by solvent-extraction and ion-exchange techniques and determined by potentiometric titration. Uranium was separated by ion exchange and determined by potentiometric titration. Solutions that were similar to the actual dissolver solutions and that contained known amounts of plutonium and uranium were analyzed by these met… more
Date: July 14, 1955
Creator: Foster, R. W.; Cooper, J. H. & Raaen, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Solid State Division Semiannual Progress Report For Period Ending February 28, 1955

Description: This semiannual progress report and future reports will be published as two documents to permit a wider distribution of the unclassified material. The report numbers are assigned in sequence so that the two reports will fall together when filed by report number.
Date: July 12, 1960
Creator: Billington, D. S. & Crawford, J. H., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Recent Developments in DC Polarography

Description: This paper summarized the work at ORNL in controlled-potential dc polarography since mid 1959 and states conclusion and viewpoints that have been reached in the course of this work. The following topics are discussed: (1) Potentiostatic Compensation for Polarographic Cell Resistance; (2) Time-Derivative DC Polarography; (3) Signal-to-Noise Ratio (S.N); (4) Resolution; and (5) DC Polarography in Non Aqueous Solvents and, Particularly, in Solvent Extracts.
Date: July 1964
Creator: Fisher, D. J.; Belew, W. L. & Kelley, M. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Some Applications of the Distorted Wave Approximation for Direct Nuclear Reactions

Description: The subject which I will discuss is the distorted - waves theory of direct reactions and its application to the study of nuclei. I shall mainly be concerned with a study of the reaction theory, its range of validity, and its ability to give quantitative information about nuclear structure.
Date: July 1964
Creator: Bassel , R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen