Monthly Report of Securities Registrations in Texas, June 1962 (open access)

Monthly Report of Securities Registrations in Texas, June 1962

Monthly newsletter of the Texas State Securities Board documenting authorization for the sale of securities in the state, listing the permit date, information about the company, and total offering for each one.
Date: July 1962
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Monthly Report of Securities Registrations in Texas, July 1962 (open access)

Monthly Report of Securities Registrations in Texas, July 1962

Monthly newsletter of the Texas State Securities Board documenting authorization for the sale of securities in the state, listing the permit date, information about the company, and total offering for each one.
Date: August 1962
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Monthly Report of Securities Registrations in Texas, August 1962 (open access)

Monthly Report of Securities Registrations in Texas, August 1962

Monthly newsletter of the Texas State Securities Board documenting authorization for the sale of securities in the state, listing the permit date, information about the company, and total offering for each one.
Date: September 1962
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Monthly Report of Securities Registrations in Texas, December 1962 (open access)

Monthly Report of Securities Registrations in Texas, December 1962

Monthly newsletter of the Texas State Securities Board documenting authorization for the sale of securities in the state, listing the permit date, information about the company, and total offering for each one.
Date: January 1963
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Monthly Report of Securities Registrations in Texas, January 1963 (open access)

Monthly Report of Securities Registrations in Texas, January 1963

Monthly newsletter of the Texas State Securities Board documenting authorization for the sale of securities in the state, listing the permit date, information about the company, and total offering for each one.
Date: February 1963
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS (open access)

The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS

Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date: September 8, 1961
Creator: Porter, E. H.
Object Type: Report
System: The UNT Digital Library
Texas State Securities Board Monthly Bulletin, December 1966 (open access)

Texas State Securities Board Monthly Bulletin, December 1966

Monthly newsletter of the Texas State Securities Board documenting authorization for the sale of securities in the state, listing the permit date, information about the company, and total offering for each one. It also includes other notices or updates about policy changes and the agency's activities.
Date: January 1967
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Texas State Securities Board Monthly Bulletin, February 1967 (open access)

Texas State Securities Board Monthly Bulletin, February 1967

Monthly newsletter of the Texas State Securities Board documenting authorization for the sale of securities in the state, listing the permit date, information about the company, and total offering for each one. It also includes other notices or updates about policy changes and the agency's activities.
Date: March 1967
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Dispersion Strengthening of Iron-Aluminum Base Alloys: A Feasibility Study (open access)

Dispersion Strengthening of Iron-Aluminum Base Alloys: A Feasibility Study

The feasibility of improving the mechanical properties at 1700-1800°F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion has been explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion characteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispersion with an interparticle spacing of about 2-3 µ. High-temperature native oxides of the Fe-Al-Cr alloy consist largely of Al2O3 and in theory would serve as a satisfactory second phase.
Date: December 27, 1960
Creator: King, Blake
Object Type: Report
System: The UNT Digital Library
ORR Startup Accident and Cooling Flow Coastdown Analog Analysis (open access)

ORR Startup Accident and Cooling Flow Coastdown Analog Analysis

Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is increased to the point where the level scram must be set above 50 Mw).
Date: January 4, 1961
Creator: Stone, R. S. & Colomb, A. L.
Object Type: Report
System: The UNT Digital Library
Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop (open access)

Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop

Simulated reactor fuel solutions were circulated at temperatures as high as 365°C in a small titanium pump loop. A hydroclone separator separated heavy phases formed at high temperatures. As the temperature of the solution was increased beyond the two-liquid-phase temperature (327°C), the salt concentration of the light phase decreased and the acid concentration increased. The mole ratios of uranium to sulfate, uranium to copper, and uranium to nickel in the light phase decreased in the same proportion in the temperature range of 330 to 365°C. Corrosion of titanium and Zircaloy-2 specimens was insignificant during the relatively short exposure periods.
Date: January 6, 1961
Creator: Griess, J. C.; Baker, J. M. & Savage, H. C.
Object Type: Report
System: The UNT Digital Library
Bremsstrahlung Absorption Measurements from Sr^90 TiO3 (open access)

Bremsstrahlung Absorption Measurements from Sr^90 TiO3

The absorption in lead of Bremsstrahlung X radiation from a Sr^90 TiO3 pellet in the proximity of Hastelloy "C" was measured. The tenth value layer of the more energetic components of the X-ray continuum was determined to be 1.60 inches.
Date: January 13, 1961
Creator: Butler, T. A. & Pierce, E. E.
Object Type: Report
System: The UNT Digital Library
Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960 (open access)

Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960

A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date: January 11, 1961
Creator: Sadowski, G. S.
Object Type: Report
System: The UNT Digital Library
Revised Version of HFIR Critical Experiment-2 (HFCE-2) (open access)

Revised Version of HFIR Critical Experiment-2 (HFCE-2)

A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date: January 16, 1961
Creator: Kasten, P. R. & Cheverton, R. D.
Object Type: Report
System: The UNT Digital Library
Some Heat Transfer Characteristics of ORR Fuel Elements (open access)

Some Heat Transfer Characteristics of ORR Fuel Elements

Analyses are generally made at the ORR with a view toward determining the surface temperatures of fuel plates.
Date: January 19, 1961
Creator: Wett, J. F., Jr.
Object Type: Report
System: The UNT Digital Library
Sources and Availability of Helium (open access)

Sources and Availability of Helium

A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date: January 19, 1961
Creator: Fraas, A. P.
Object Type: Report
System: The UNT Digital Library
Xenon and Samarium Poisoning (open access)

Xenon and Samarium Poisoning

The equilibrium and maximum override values for xenon and samarium poisoning have been computed using the recently issued effective cross sections of C. H. Westcott. Values are given as a function of specific power, neutron temperature, and epithermal flux content.
Date: January 23, 1961
Creator: Carlsmith, R. S.
Object Type: Report
System: The UNT Digital Library
A Useful Solution for Short Cylindrical Shells and Other Applications (open access)

A Useful Solution for Short Cylindrical Shells and Other Applications

The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notation is used throughout the derivations; however, a knowledge of matrix theory is not need for application of the results.
Date: February 14, 1961
Creator: Moore, S. E.
Object Type: Report
System: The UNT Digital Library
Pressure Vessel Exposure to Fast Neutrons (open access)

Pressure Vessel Exposure to Fast Neutrons

In a gas-cooled reactor operating at very high power density the thickness of the reflector may be determine by the requirement that the steel pressure vessel be protected from an excessive dose of fast neutrons, rather than by the usual requirements of neutron economy and power distribution. It is important the the reflector not be made thicker than necessary, since an increase in pressure vessel diameter can result in a marked increase in cost, as well as a decrease in the permitted gas pressure level.
Date: January 21, 1960
Creator: Carlsmith, R. S.
Object Type: Report
System: The UNT Digital Library
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962 (open access)

Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962

The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors.
Date: October 25, 1962
Creator: Howard, C. L.
Object Type: Report
System: The UNT Digital Library
High Power Density Development Project Tenth Quarterly Progress Report July-September 1962 (open access)

High Power Density Development Project Tenth Quarterly Progress Report July-September 1962

The Big Rock Point Reactor of the Consumers Power Company went critical for the first time on September 27, 1962. Summarized here are objectives and accomplishments of the pre-operational period as well as an indication of work scope remaining.
Date: October 1, 1962
Creator: Holladay, R. L.
Object Type: Report
System: The UNT Digital Library
Heavy Element Isotopic Analysis of UO2 Fuel Irradiated In The VBWR: Report #1 (open access)

Heavy Element Isotopic Analysis of UO2 Fuel Irradiated In The VBWR: Report #1

The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of uranium oxide fuel in a boiling water reactor.
Date: December 28, 1962
Creator: Hackney, M. R. & Ruiz, C. P.
Object Type: Report
System: The UNT Digital Library
Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program (open access)

Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program

The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.
Date: December 5, 1962
Creator: Antony, K. C. & Jones, L. T.
Object Type: Report
System: The UNT Digital Library
The Measurement Of Free Fission Gas Pressure In Operating Reactor Fuel Elements (open access)

The Measurement Of Free Fission Gas Pressure In Operating Reactor Fuel Elements

The experimental program described has had as its objective the determination of the pressure exerted by free fission gas in operating UO2-filled reactor fuel elements.
Date: January 23, 1963
Creator: Reynolds, M. B.
Object Type: Report
System: The UNT Digital Library