Resource Type

States

Flight investigation of pentaborane fuel in 9.75-inch-diameter ram-jet engine with downstream fuel injection (open access)

Flight investigation of pentaborane fuel in 9.75-inch-diameter ram-jet engine with downstream fuel injection

Report presenting a flight test of pentaborane fuel in an air-launched ramjet engine with a design free-stream Mach number of 1.8. The ramjet used in the investigation had a revised spray bar-flameholder configuration. Results regarding propulsive thrust and propulsive-thrust specific fuel consumption are provided.
Date: April 22, 1957
Creator: Disher, John H. & Jones, Merle L.
Object Type: Report
System: The UNT Digital Library
Flight Investigation of Pentaborane Fuel in 9.75-inch-diameter Ram-jet Engine With Downstream Fuel Injection (open access)

Flight Investigation of Pentaborane Fuel in 9.75-inch-diameter Ram-jet Engine With Downstream Fuel Injection

Flight investigation of pentaborane fuel in 9.75- inch-diameter ramjet engine with downstream fuel injection.
Date: April 22, 1957
Creator: Disher, John H. & Jones, Merle L.
Object Type: Report
System: The UNT Digital Library
Full-Scale Investigation of Several Jet-Engine Noise-Reduction Nozzles (open access)

Full-Scale Investigation of Several Jet-Engine Noise-Reduction Nozzles

"A number of noise-suppression nozzles were tested on full-scale engines. In general, these nozzles achieved noise reduction by the mixing interference of adjacent jets, that is, by using multiple-slot-nozzles. Several of the nozzles achieved reductions in sound power of approximately 5 decibels (nearly 70 percent) with small thrust losses (approx. 1 percent). The maximum sound-pressure level was reduced by as much as 18 decibels in particular frequency bands" (p. 1249).
Date: January 22, 1957
Creator: Coles, Willard D. & Callaghan, Edmund E.
Object Type: Report
System: The UNT Digital Library
Some Calculations of Diffusion Controlled Thermal Gradient Mass Transfer (open access)

Some Calculations of Diffusion Controlled Thermal Gradient Mass Transfer

Calculations are presented of the amount of mass transfer to be expected in liquid alkali metal-Ni alloy systems for two assumed diffusion mechanisms. In one, the boundary layer is assumed saturated and the transfer rate is limited by the rate of diffusion of solute into the liquid. In the other, the mass transfer rate is assumed to be limited by the diffusion rate of a component of the solid alloy to the solid surface. It is concluded tbat a more general hypothesis is needed. (T.R.H.)
Date: July 22, 1957
Creator: Keyes, J.J. Jr.
Object Type: Report
System: The UNT Digital Library
Irradiation Testing Facilities at the Hanford Atomic Products Operation (open access)

Irradiation Testing Facilities at the Hanford Atomic Products Operation

A wide range of irradiation testing facilities and services are present at the Hanford Atomic Products Operation. A number of these facilities are described as a means of illustrating the testing equipment and techniques which are currently in use. (auth)
Date: May 22, 1957
Creator: Blasewitz, A. G.
Object Type: Report
System: The UNT Digital Library
Summary of Corrosion Data for HRT Mockup Operational Period Ending November 5, 1956 (open access)

Summary of Corrosion Data for HRT Mockup Operational Period Ending November 5, 1956

None
Date: May 22, 1957
Creator: Wacker, R. E. & Griess, J. C.
Object Type: Report
System: The UNT Digital Library
The Physics of the Fused-Salt Reactor Experiment (open access)

The Physics of the Fused-Salt Reactor Experiment

In 1954 the Oak Ridge Nationai Laboratory operated, for demonstration purposes, a high-temperature circulatingfuel reactor, employing as fuel enriched uranium fluoride dissolved in molten fluorides of other cations. A BeO moderator was used. At a maximum power of 2.5 Mw, 100 Mw hr were obtained. A negative temperature coefficient resulting largely from fuel expansion yielded exceptional stability of the reactor, and made the reactor a slave of the power demand. Xe/ sup 135/ and some of the other fission fragments are not retained in the fuel; hence, there is no xenon poisoning and relatively little danger of spreading of gaseous fission fragments in case of an accident. The advantages of liquid-fuel reactors (elimination of radiation dnmage and thermal stresses in solid fuel elements, ease of fabrication and fuel reprocessing) are combined with low pressures at very high temperatures. (auth)
Date: February 22, 1957
Creator: Ergen, W.K.
Object Type: Report
System: The UNT Digital Library
DEFLECTION EQUATIONS FOR VARIOUS LOADINGS OF CIRCULAR-ARC CURVED BEAMS (open access)

DEFLECTION EQUATIONS FOR VARIOUS LOADINGS OF CIRCULAR-ARC CURVED BEAMS

None
Date: April 22, 1957
Creator: Platus, D.L. & Greenstreet, B.L.
Object Type: Report
System: The UNT Digital Library
IN-REACTOR AUTOCLAVE CORROSION STUDIES-LITR. I. OUTLINE OF METHODS AND PROCEDURES (open access)

IN-REACTOR AUTOCLAVE CORROSION STUDIES-LITR. I. OUTLINE OF METHODS AND PROCEDURES

None
Date: May 22, 1957
Creator: Warren, K.S. & Davis, R.J.
Object Type: Report
System: The UNT Digital Library
High-Temperature Oxidation Resistance of Thin Iron-Chromium-Aluminum Alloy Sheet (open access)

High-Temperature Oxidation Resistance of Thin Iron-Chromium-Aluminum Alloy Sheet

Abstract: "The oxidation resistance of thin sheets of iron-28 w/o chromium-2.67 to 10.0 w/o alloys, nominally 0.004, 0.006, 0.008, 0.012, and 0.016 in. thick, was determined by exposure in static air for 100 hr at 2100 and 2300 F. A minimum of 3.67 and 9.37 w/o aluminum was necessary to prevent excessive oxidation of 0.004-in.-thick sheet material at 2100 and 2300 F, respectively. Correspondingly, specimens of lower aluminum content and greater thickness withstood the oxidation attack. Oxidation of iron-chromium-aluminum alloys appeared to be related to the diffusion of aluminum to surfaces of the sheet to form an adherent protective layer of Al2O3."
Date: October 22, 1957
Creator: Jablonowski, Edward J.; Shober, Frederic R. & Dickerson, Ronald F.
Object Type: Report
System: The UNT Digital Library
Beryllium-oxide : [bibliography] (open access)

Beryllium-oxide : [bibliography]

"This is a bibliography of journal articles relating to beryllium oxide. Sources consulted include; Chemical Abstracts, 1951-1955; Physics Abstracts, 1951-1955; Industrial Arts Index, 1955-Jan, 1957; and the library card catalog. Starred articles are available in the library.
Date: March 22, 1957
Creator: Cason, Maggie
Object Type: Report
System: The UNT Digital Library
Chemical Processing Department monthly report, April 1957 (open access)

Chemical Processing Department monthly report, April 1957

Two new production records were set during April, for processed U and Pu production. 0.9 tons sheared NRX fuel were dissolved in Redox. Discrepancies in Pu yield are being studied. Alternate methods of recovering Np are being evaluated. The Purex prototype facility will be converted to the anion exchange process. Alternate designs for a Purex miniature service dissolver were reviewed. The Purex HA column will be replaced.
Date: May 22, 1957
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Chemical Processing Department monthly report, June 1957 (open access)

Chemical Processing Department monthly report, June 1957

Purex and Redox plants operated satisfactorily. Pu production exceeded commitments. The continuous calciners in UO{sub 3} plant experienced difficulty, but the monthly commitment was exceeded. Capital costs for conversion of B plant to recover Cs and Ce have increased. For future processing of E metal, several 3-ton batches were dissolved in Redox. The continuous Task I prototype is being tested for startup of production facilities. Redox product solutions generally have higher waste losses than these from Purex material. The continuous anion exchange prototype will also be tested. Engineering studies were completed of two facets of Purex Phase II expansion, plant conversion to two cycles, and expansion to a rate of 25.8 tons U/day. A proposal requests authority to expand Purex to capacity factor 3.2 along with the two-cycle conversion. The Pu trifluoride process review indicated that conversion to the PuF3 process is not likely. Separations plant dissolver capacity potential for the next 5 yr was studied. (DLC)
Date: July 22, 1957
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Discussion of Slurry Problems with Dr. W. 0. Milligan (open access)

Discussion of Slurry Problems with Dr. W. 0. Milligan

None
Date: April 22, 1957
Creator: Morgan, C. S.
Object Type: Report
System: The UNT Digital Library
High-Temperature Oxidation Resistance of Thin Iron-Chromium-Aluminum Alloy Sheet (open access)

High-Temperature Oxidation Resistance of Thin Iron-Chromium-Aluminum Alloy Sheet

S>The oxidation resistance of thin sheets of Fe - 28 wt. % Cr - 2.67 to 10.0 wt. % Al alloys, nominally 0.004, 0.006, 0.008, 0.012, and 0.016 in. thick, was determined by exposure in static air for 100 hr at 2100 and 2300 deg F. A minimum of 3.67 and 9.37 wt.% Al was necessary to prevent excessive oxidation of 0.004-in. thick sheet material at 2100 and 2300 deg F, respectively. Specimens of lower Al content and greater thickness withstood oxidation attack. Oxidation of Fe - Cr - Al alloys apperars to be related to the diffusion of Al to surfaces of the sheet to form an adherent protective layer of Al/sub 2/ O/sub 3/.(auth)
Date: October 22, 1957
Creator: Jablonowski, E. J.; Shober, F. R. & Dickerson, R. F.
Object Type: Report
System: The UNT Digital Library
Experiments on Antiprotons: Cross Sections of Complex Nuclei (open access)

Experiments on Antiprotons: Cross Sections of Complex Nuclei

Experiments are described that have been designed to measure separately annihilation and reaction cross sections for antiprotons of approximately 450 MeV on oxygen, copper, silver, and lead. A new and more luminous spectrograph has been built for this experiment. The antiproton cross sections a r e compared with total proton cross sections, and are found to be larger by a factor varying from 1.74 for oxygen to 1.39 for silver. Calculations based on the optical model give a reasonable connection between these cross sections and the 6-p and 6-n cross sections. Finally, the information available on antiproton production cross sections is collected. There are indications that a free nucleon is several times as effective as a bound one for producing antiprotons.
Date: July 22, 1957
Creator: Agnew, Jr., Lewis E.; Chamberlain, Owen; Keller, Donald V.; Mermod, Ronald; Rogers, Ernest H.; Steiner, Herbert M. et al.
Object Type: Report
System: The UNT Digital Library
NIOBIUM-URANIUM ALLOYS AS CONTAINER MATERIAL FOR MOLTEN URANIUM EUTECTIC ALLOYS (open access)

NIOBIUM-URANIUM ALLOYS AS CONTAINER MATERIAL FOR MOLTEN URANIUM EUTECTIC ALLOYS

A previous investigation concerned with liquid-core fuel elements and the materials from which they could be constructed revealed tht an alloy of U--5 wt. % Nb had considerable promise as container material. Results are given from a further investigation of this alloy, as well as another containing 10 wt. % Nb, to determine the time and temperature limits within which tbe oxide layer remains protective, the factors which hasten or delay the breakdown of the film, and the mechanism whereby the film deteriorites, (auth)
Date: August 22, 1957
Creator: Powell, G. W.
Object Type: Report
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1956-January 1957 (open access)

Homogeneous Reactor Project Quarterly Progress Report: November 1956-January 1957

Report issued by the Oak Ridge National Laboratory discussing quarterly progress of the Homogeneous Reactor Project. Progress of operations, design, development, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: April 22, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Bruce, F. R. et al.
Object Type: Report
System: The UNT Digital Library
Preliminary Investigations for an Advanced Engineering Test Reactor (open access)

Preliminary Investigations for an Advanced Engineering Test Reactor

Study carried out to determine a suitable reactor system or systems for the testing of water, gas, and liquid-metal cooled fuel assemblies.
Date: February 22, 1957
Creator: Elgert, O. J.; Leyse, C. F. & Ott, D. G.
Object Type: Report
System: The UNT Digital Library
Investigation of two-stage air-cooled turbine suitable for flight at Mach number of 2.5 2: blade design (open access)

Investigation of two-stage air-cooled turbine suitable for flight at Mach number of 2.5 2: blade design

A blade design study is presented for a two-stage air-cooled turbine suitable for flight at a Mach number of 2.5 for which velocity diagrams have been previously obtained. The detailed procedure used in the design of the blades is given. In addition, the design blade shapes, surface velocity distributions, inner and outer wall contours, and other design data are presented. Of all the blade rows, the first-stage rotor has the highest solidity, with a value of 2.289 at the mean section. The second-stage stator also had a high mean-section solidity of 1.927, mainly because of its high inlet whirl. The second-stage rotor has the highest value of the suction-surface diffusion parameter, with a value of 0.151. All other blade rows have values for this parameter under 0.100.
Date: January 22, 1957
Creator: Miser, James W. & Stewart, Warner L.
Object Type: Report
System: The UNT Digital Library
Preliminary evaluation of pentaborane in a 1/4-sector of an experimental annular combustor (open access)

Preliminary evaluation of pentaborane in a 1/4-sector of an experimental annular combustor

Report presenting an evaluation of a 1/4-sector of an annular combustor designed for use with pentaborane fuel at a simulated altitude condition. Results regarding the pentaborane performance, combustor development, and the JP-5 fuel performance are provided.
Date: May 22, 1957
Creator: Kaufman, Warner B.; Lezberg, Erwin A. & Breitwieser, Roland
Object Type: Report
System: The UNT Digital Library
Drag of Conical and Circular-Arc Boattail Afterbodies at Mach Numbers From 0.6 to 1.3 (open access)

Drag of Conical and Circular-Arc Boattail Afterbodies at Mach Numbers From 0.6 to 1.3

"Drag characteristics of a series of related conical and circular-arc afterbodies are presented for Mach numbers from 0.6 to 1.3. Drag was obtained from pressure measurements on the boattail and solid base. The boattail angles tested ranged from 0 degrees to 45 degrees for ratios of base diameter to maximum body diameter ranging from 0 to 1.0" (p. 1).
Date: January 22, 1957
Creator: Silhan, Frank V. & Cubbage, James M., Jr.
Object Type: Report
System: The UNT Digital Library
Investigation of axially symmetric flow over steps at transonic speeds with comparisons of estimated and experimental drag results (open access)

Investigation of axially symmetric flow over steps at transonic speeds with comparisons of estimated and experimental drag results

Report presenting an investigation of the problem of predicting the experimental wave drag for configurations which have discontinuities in area distribution and thus infinite theoretical wave drag. The agreement between the experimental and computed drags of the ring-body combinations without fillets was very poor. Results regarding the drag coefficients and estimation of wave drag and pressure coefficients and estimation of total drag are provided.
Date: July 22, 1957
Creator: Holdaway, George H. & Wallace, Minor R., Jr.
Object Type: Report
System: The UNT Digital Library
Some Properties of Wing and Half-Body Arrangements at Supersonic Speeds (open access)

Some Properties of Wing and Half-Body Arrangements at Supersonic Speeds

Report presenting an investigation of the certain wing-body combinations as measured by the lift-drag ratio for two arrangements: a half-cone mounted under a triangular wing and a half Newtonian ogive similarly mounted. The configurations were tested for a range of Mach numbers from 1.5 to 5.0. Results regarding the comparison of a half-cone versus a full cone and calculated maximum lift-drag ratio are provided.
Date: July 22, 1957
Creator: Migotsky, Eugene & Adams, Gaynor J.
Object Type: Report
System: The UNT Digital Library