Analyses for Turbojet Thrust Augmentation With Fuel-Rich Afterburning of Hydrogen, Diborane, and Hydrazine (open access)

Analyses for Turbojet Thrust Augmentation With Fuel-Rich Afterburning of Hydrogen, Diborane, and Hydrazine

Turbojet thrust augmentation with fuel-rich afterburning of hydrogen, diborane, and hydrazine was computed. Results regarding takeoff thrust augmentation and flight thrust augmentation are provided.
Date: June 18, 1957
Creator: Morris, James F.
Object Type: Report
System: The UNT Digital Library
Analyses for turbojet thrust augmentation with fuel-rich afterburning of hydrogen, diborane, and hydrazine (open access)

Analyses for turbojet thrust augmentation with fuel-rich afterburning of hydrogen, diborane, and hydrazine

From Introduction: "This report presents net thrusts computed for hydrogen, diborance, and hydrazine with fuel-air ratios form stoichiometric values to 0.5. Net thrusts for fuel-rich afterburning are compared with those for stoichiometric combustion of the turbojet fuel and air augmented with a 220-second specific-impulse rocket."
Date: June 18, 1957
Creator: Morris, James F.
Object Type: Report
System: The UNT Digital Library
Continuous dissolution of uranium fuel elements in a tower dissolver (open access)

Continuous dissolution of uranium fuel elements in a tower dissolver

A continuous process for the dissolution of irradiated fuel elements is a potential means of solving criticality limitations in the dissolution of enriched uranium slugs and of achieving higher dissolver capacity in the Redox and Purex Plants. This report summarizes development studies aimed at determination of dissolution rates, effluent compositions, and effects of changes in operating conditions on mercury-catalyzed dissolution in a tower-type unit.
Date: June 18, 1957
Creator: Evans, T. F.
Object Type: Report
System: The UNT Digital Library
Distribution of Radiation Damage in Graphite (open access)

Distribution of Radiation Damage in Graphite

None
Date: June 18, 1957
Creator: Nightingale, R. E. & Snyder, W. A.
Object Type: Report
System: The UNT Digital Library
INCONEL AS A STRUCTURAL MATERIAL FOR A HIGH-TEMPERATURE FUSED-SALT REACTOR (open access)

INCONEL AS A STRUCTURAL MATERIAL FOR A HIGH-TEMPERATURE FUSED-SALT REACTOR

The use of a circulating-fuel type of nuclear reactor as an energy source in aircraft propulsion systems imposes upon the structural material metallurgical restrictions which limit the applicability of certain types of alloys. The general factors which must be considered in the selection of an alloy for this application are corrosion resistance, fabricability, nuclear properties, radiation damage, and elevated-temperature strength, The importance of each of these topics is pointed out, and it is shown that the selection of Iconel ss a structural material was based on these criteria (auth)
Date: June 18, 1957
Creator: Weir, J. R., Jr.; Douglas, D. A. & Manly, W. D.
Object Type: Report
System: The UNT Digital Library
The Influence of Lubrication on the Compactability of Magnesium-Green Salt Blends for Bomb Reduction (open access)

The Influence of Lubrication on the Compactability of Magnesium-Green Salt Blends for Bomb Reduction

Lubrication of die surfaces with mineral oil or Dag 217 during final compacting of UF/sub 4/--Mg blends prevented seizing. Mineral oil application after every third press allowed 18 compacts before seizing became severe. Similar application of Dag 217 allowed 78 compacts. Mixing 0.33 wt.% Ceremul "C" with the powder allowed 40 compacts. Punch clearance had little effect on seizing. (T.R.H.)
Date: June 18, 1957
Creator: Paprocki, S. J.; Carlson, R. J. & Smith, E. G., Jr.
Object Type: Report
System: The UNT Digital Library
The Influence of Lubrication on the Compactability of Magnesium-Green Salt Blends for Bomb Reduction (open access)

The Influence of Lubrication on the Compactability of Magnesium-Green Salt Blends for Bomb Reduction

The following report follows the procedures to compact blends of uranium tetrafluoride and magnesium, describing how lubrication of the compact effects the outcome of the blends.
Date: June 18, 1957
Creator: Paprocki, Stan J.; Carlson, Ronald J. & Smith, Edward G., Jr.
Object Type: Report
System: The UNT Digital Library
Liquid-Liquid Extraction of Uranium and Plutonium from Hydrochloric Acid Solution with TRI (Iso-Octyl) Amine.  Separation of Uranium and Plutonium from Thorium and Fission Products (open access)

Liquid-Liquid Extraction of Uranium and Plutonium from Hydrochloric Acid Solution with TRI (Iso-Octyl) Amine. Separation of Uranium and Plutonium from Thorium and Fission Products

A new and rapid method for the liquid-liquid extraction of uranium and plutonium from hydrochloric acid solution is based on the use of tri(iso-octyl)amine dissolved in xylene or methylisobutylketone. Uranium and/or plutonium are separated from thorium, alkalis, alkaline earths, rare earths, zirconium, niobium, ruthenium and other elements which do not form anionic species under the conditions described. The technique may be used for either tracer or macro quantities of uranium. Several practical applications of the method for the separations chemist are proposed.
Date: June 18, 1957
Creator: Moore, Fletcher L.
Object Type: Report
System: The UNT Digital Library
A Method of Computing the Transient Temperature of Thick Walls From Arbitrary Variation of Adiabatic-Wall Temperature and Heat-Transfer Coefficient (open access)

A Method of Computing the Transient Temperature of Thick Walls From Arbitrary Variation of Adiabatic-Wall Temperature and Heat-Transfer Coefficient

"A method of calculating the temperature of thick walls has been developed in which the time series and the response to a unit triangle variation of surface temperature concepts are used, together with essentially standard formulas for transient temperature and heat flow into thick walls. The method can be used without knowledge of the mathematical tools of its development. The method is particularly suitable for determining the wall temperature in one-dimensional thermal problems in aeronautics where there is a continuous variation of the heat-transfer coefficient and adiabatic-wall temperature" (p. 877).
Date: June 18, 1957
Creator: Hill, P. R.
Object Type: Report
System: The UNT Digital Library
New Beta Heat-Treating Salt Baths for Reducing Hydrogen Pickup by Uranium Rods (open access)

New Beta Heat-Treating Salt Baths for Reducing Hydrogen Pickup by Uranium Rods

The following report summarizes the results of the laboratory-scale work and pilot-plant scale work of a salt-batch composition that reduces the hydrogen pickup by uranium rods during the beta heat treatment, and the study of the influence of humidity over the salt bath on hydrogen pickup.
Date: June 18, 1957
Creator: Lortscher, Lawrence L.; Sense, Karl A. & Filbert, Robert B., Jr.
Object Type: Report
System: The UNT Digital Library
New Beta Heat-Treating Salt Baths for Reducing Hydrogen Pickup by Uranium Rods (open access)

New Beta Heat-Treating Salt Baths for Reducing Hydrogen Pickup by Uranium Rods

BS> Hydrogen pickup by U was studied in different salt mixtures at 1350 deg F under dry and wet atmospheres. Of the salts investigdted, 50 wt.% KCl-50 wt.% NaCl and 50 wt.% KCl-50 wt.% Na/sub 2/CO/sub 3/ gave the best results for low H pickup, corrosion of U, and salt stability at 1350 deg F. These salt mixtures resulted in H pickup of less than 3 ppm under dry atmospheres and less than 5 ppm under wet atmospheres. By comparison, the two salt mixtures, 44 wt.% Li/sub 2/CO/sub 3/-56 wt.% K/sub 2/CO/sub 3/ and 25 wt.% Li/sub 2/CO/sub 3/--75 wt.% K/sub 2/CO/sub 3/, resulted in H pickup greater than 5 ppm under dry atmospheres and as high as 13 ppm under wet atmospheres. Pilot-plantscale studies showed that the average final H content of the U specimens treated in the 50 wt.% KCl-50 wt.% NaCl baths was 0.47 ppm. The corresponding average for the 50 wt.% KCl-50 wt.% Na/sub 2/CO/sub 3/ baths was 0.77 ppm. Preliminary studies of corrosion of materials of construction in the pilot-plant-scale baths indicated that Type 330 stainless steel was more resistant to attack than mild steel and Types 304, 416, and 446 stainless steels. (auth)
Date: June 18, 1957
Creator: Lortscher, L. L.; Sense, K. A. & Filbert, R. B., Jr.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-160 (open access)

Texas Attorney General Opinion: WW-160

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Is the Comptroller authorized to issue warrant in the amount of $300.00 for the month of May against the monies appropriated for the current biennium to the one pensioner affected by House Bill 100?
Date: June 18, 1957
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-164 (open access)

Texas Attorney General Opinion: WW-164

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Construction of Article 14.25 of the Insurance Code of Texas as to what attorneys' fees and other defense expenses may be paid out of the mortuary or relief funds, subject to the approval of the Board of Insurance Commissioners.
Date: June 18, 1957
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-166 (open access)

Texas Attorney General Opinion: WW-166

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Certain questions concerning the Commissioner of Insurance as provided for in Senate Bill 222.
Date: June 18, 1957
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
A TRACER STUDY OF THE TRANSPORT OF CHROMIUM IN FLUORIDE FUEL SYSTEMS (open access)

A TRACER STUDY OF THE TRANSPORT OF CHROMIUM IN FLUORIDE FUEL SYSTEMS

An experimental study was made of the mass transport of chromium in poly- thermal Inconel-fluoride fuel systems. The transport of chromium was followed by toe technique of adding radioactive Cr/sup 51/ to the system as either CrF/sub 2/ , in the salt or as elemental chromium in the solid phase. The rates of diffusion of chromium in Inconel at 600, 700, 800, and 900 deg C were determined by an electropolishing technique. Polythermal studies were carried out by three methods, tilting capsules, thermal-convection loops, and pumping loops. Tilting- capsule experiments indicated that the preferred location for chromium deposition on the wall was in the region of maximum temperature but the conclusions were not clear cut. Thermal convection loops operated for 125 and 288 hr showed radioactivity profile which could be attributed to simple exchange, with some distortion in the 288 hr case. The duration of these experiments was evidently insufficient io allow equilibrium to be reached in the salt. A thermal- convection loop operated for 400 hr showed distortion in the exchange radioactivity profile which indicated a favorable position for chromium deposition at a point about 100 deg F below the maximum wall temperature, and on the upstream side of …
Date: June 18, 1957
Creator: Price, Robert B.; Sunderman, Duane N.; Pobereskin, Meyer & Calkins, George D.
Object Type: Report
System: The UNT Digital Library
A Tracer Study of the Transport of Chromium in Fluoride Fuel Systems (open access)

A Tracer Study of the Transport of Chromium in Fluoride Fuel Systems

The following report follows an experimental study that was made on the mass transport of chromium in polythermal inconel-fluoride fuel systems, followed by the technique of adding radioactive chromium-51 to the system as either CrF3 in the salt or as elemental chromium in the solid phase.
Date: June 18, 1957
Creator: Price, Robert B.; Sunderman, Duane Neuman; Pobereskin, Meyer & Calkins, George D.
Object Type: Report
System: The UNT Digital Library
Trip to Selas Corporation of America (open access)

Trip to Selas Corporation of America

On May 23, 1957, a visit was made by the writer to the Selas Corporation of American in Dresher, Pennsylvania. The purpose of the visit was to discuss further investigations into methods of tubesheet brazing by direct heating. Original work along these lines has been carried out at ORNL and is covered by a memo (CF-57-4-57) to W.D. Manly, dated April 16, 1957, and entitled : Investigation of Tubesheet Brazing by a Method of Direct Heating.
Date: June 18, 1957
Creator: Franco-Ferreira, E. A.
Object Type: Report
System: The UNT Digital Library
TRIP TO SELAS CORPORATION OF AMERICA, MAY 23, 1957, TO DISCUSS INVESTIGATIONS INTO METHODS OF TUBESHEET BRAZING BY DIRECT HEATING (open access)

TRIP TO SELAS CORPORATION OF AMERICA, MAY 23, 1957, TO DISCUSS INVESTIGATIONS INTO METHODS OF TUBESHEET BRAZING BY DIRECT HEATING

None
Date: June 18, 1957
Creator: Franco-Ferreira, E.A.
Object Type: Report
System: The UNT Digital Library