EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment (open access)

EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment

The measurements reported here are companion measurements to those reported earlier in HW-63585. The only significant difference between the measurements is that 1.8 w/o enrichment UO2 fuel was used for the first set, and 2.6 w/o enrichment UO2 fuel was used for the measurements described in this report. The new results will be presented graphically, and for completeness, the details of the measurement will be included here as well as in HW-63585.
Date: May 10, 1960
Creator: Nichols, P. F.
Object Type: Report
System: The UNT Digital Library
Aluminum Alloy Work at Hanford (open access)

Aluminum Alloy Work at Hanford

Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
Date: May 6, 1960
Creator: Bowen, H. C.
Object Type: Report
System: The UNT Digital Library
Unclassified Research and Development Programs Executed for the Division of Reactor Development and the Division of Research April 1960 (open access)

Unclassified Research and Development Programs Executed for the Division of Reactor Development and the Division of Research April 1960

A 19-rod Zircaloy-clad half-length PRTR spike element successfully irradiated to high plutonium burnout at full power in the ETR shoved partial bonding of the core and cladding. Unsatisfactory autoclave films on the Zircaloy cladding of the PRTR Al-Pu fuel elements are delaying final assembly of the first 30 clusters. Further conditioning of the autoclaves and the availability of permanent etching facilities are expected to correct the present difficulties.
Date: May 10, 1960
Creator: Hanford Laboratories Operation Irradiation Procesing Department
Object Type: Report
System: The UNT Digital Library
L/R Indicator (open access)

L/R Indicator

The evaluation of the inductance of an electrical component is often important in understanding and operating an electrical circuit. Inductance is defined by several equations, the most common being e= -L d1/dt . This equation defines inductance as the constant which relates the back emf produced in an element to the time-rate-of-change of current.
Date: May 20, 1960
Creator: Minor, G. C.
Object Type: Report
System: The UNT Digital Library
DETERMINATION OF THE TRUE STRESS-STRAIN PROPERTIES OF BRITTLE MATERIALS TO 5000 F. Ninth Monthly Report (open access)

DETERMINATION OF THE TRUE STRESS-STRAIN PROPERTIES OF BRITTLE MATERIALS TO 5000 F. Ninth Monthly Report

The development of the system and techniques to permit determination of strains at right angle to the axis of loading in the specimen was continued. An additional optical system was developed to accept the lateral image of the gage points and project a vertical image of the same proportion to the apertures of the strain analyzer. Using a dummy specimen of steel in the load train, the automatic pressure control system for the gas-bearing universals was operated. A fluctuation of gas pressure occurred within the bearings. Multiple progressive fracture planes were observed throughout the gage length of fractured graphite and tungsten. (M.C.G.)
Date: May 17, 1962
Creator: Digesu, F.J. & Pears, C.D.
Object Type: Report
System: The UNT Digital Library
Calculated Scattering Kernels For Light Water at 23C, 42C, 61C, and 82C (open access)

Calculated Scattering Kernels For Light Water at 23C, 42C, 61C, and 82C

This report contains a listing of the bound-proton kernels for neutron scattering which were calculated in conjunction with the USAEC Control Rod Materials Program.
Date: May 27, 1962
Creator: Kerr, B. A.
Object Type: Report
System: The UNT Digital Library
Evaluation of fuel particles (open access)

Evaluation of fuel particles

None
Date: May 25, 1965
Creator: Feild, A. L., Jr. & Brizes, W.F.
Object Type: Report
System: The UNT Digital Library
A Tabulation of the Specific Heat Contribution Due to Thermal Excitation (Schottky Effect) of the 4f Electrons of Some Di- and Tri-Valent Lanthanide Elements (open access)

A Tabulation of the Specific Heat Contribution Due to Thermal Excitation (Schottky Effect) of the 4f Electrons of Some Di- and Tri-Valent Lanthanide Elements

None
Date: May 1, 1965
Creator: Dennison, D. H. & Gschneidner, K. A., Jr.
Object Type: Report
System: The UNT Digital Library
Evaluation of low assay Pu-238 oxide for use in fabrication of plasma-fired microspheres (open access)

Evaluation of low assay Pu-238 oxide for use in fabrication of plasma-fired microspheres

The desirability of evaluating low assay plutonium-238 ({approximately}23% Pu-238) oxide was discussed with AEC personnel during a meeting at Germantown on July 6, 1967. In September, 1967 a sample of this material was furnished to Mound for evaluation. This evaluation was to be completed on a schedule which would not interfere with production of material for the SNAP programs, and was to include characterization of the oxide feed, and preparation and subsequent characterization of plasma-fired microspheres according to SNAP-27 procedures. Authorization to perform this work was received from DAO on September 1, 1967.
Date: May 15, 1968
Creator: Madding, R. D., Jr. & Vallee, R. E.
Object Type: Report
System: The UNT Digital Library
Studies of Metal-Water Reactions at High Temperatures: I. The Condenser Discharge Experiment: Preliminary Results With Zirconium (open access)

Studies of Metal-Water Reactions at High Temperatures: I. The Condenser Discharge Experiment: Preliminary Results With Zirconium

The condenser-discharge method of conducting molten metal- water reactions at high temperatures was refined. Two methods to measure energy input to specimen wires and, therefore, to compute initial metal temperatures were developed. Calculated metal temperatures were estimated to be accurate to within 100 deg C. Two reaction cells were designed, one for operation at atmospheric pressure with water at room temperature, and the other for operation at high pressure and with water at elevated temperature. Means were developed to determine the surface area of metal exposed to reaction and to determine the total extent of reaction. Pressure transducers were used to record the rate of reactions. The zirconium- water reaction was studied with initial metal temperatures from 1100 to 4000 deg C with 30 and 60-mil wires in room-temperature water. Initial pressures in these runs were the vapor pressures of water at room temperature (20-30 mm). Runs were made with 60-mil wires in water heated to 200 deg C (225 psi). Results in room-temperature water indicated that the reaction became explosive at an initial metal temperature of 2600 deg C. Below this temperature, 20% or less reaction occurred. At higher water temperatures, reaction ranged from 40 to 70%. Runs in …
Date: May 1, 1961
Creator: Baker, L., Jr.; Warchal, R.L.; Vogel, R.C. & Kilpatrick, M.
Object Type: Report
System: The UNT Digital Library
Petroleum Production, Drilling and Leasing on the Outer Continental Shelf: A Summary (open access)

Petroleum Production, Drilling and Leasing on the Outer Continental Shelf: A Summary

This report is about the submerged lands and the occurrence of petroleum deposits.
Date: May 1966
Creator: United States. Department of the Interior.
Object Type: Report
System: The UNT Digital Library
Economic Evaluation of Control Rod Materials and Fabrication Processes (open access)

Economic Evaluation of Control Rod Materials and Fabrication Processes

Control rod materials, designs, and fabrication processes are compared for their relative economies. Control rod lifetime data are calculated with a simple approximation of nuclear worth depreciation. These data are used in conjunction with the estimated fabrication costs to determine the cost of using several absorber materials in a typical power reactor on a cost-per-year basis. The effect the control system has on core power density and fuel lifetime is included.
Date: May 1962
Creator: Williamson, H. E. & Megerth, F. H.
Object Type: Report
System: The UNT Digital Library
Texas Business Review, Volume 37, Issue 5, May 1963 (open access)

Texas Business Review, Volume 37, Issue 5, May 1963

Newsletter of the University of Texas Bureau of Business Research outlining statistics and research related to business in Texas.
Date: May 1963
Creator: University of Texas. Bureau of Business Research.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Texas Business Review, Volume 39, Issue 5, May 1965 (open access)

Texas Business Review, Volume 39, Issue 5, May 1965

Newsletter of the University of Texas Bureau of Business Research outlining statistics and research related to business in Texas.
Date: May 1965
Creator: University of Texas. Bureau of Business Research.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod (open access)

Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod

Previously reported results on the testing of small samples of boron carbide dispersed in nickel by electrolytic codeposition were adequately encouraging to lead to the development of a prototype control rod for operation in the Vallecitos Boiling Water Reactor. The operation of the control rod has been entirely satisfactory.
Date: May 1962
Creator: Williamson, H.E. & Alexander, A. J.
Object Type: Report
System: The UNT Digital Library
Physics Calculations for the Consumers Big Rock Point Process Computer (open access)

Physics Calculations for the Consumers Big Rock Point Process Computer

The physics calculations to be performed on the Consumers On-Line Process Computer are reported. As a result of these calculations, a three-dimensional power shape is simulated, a reactivity balance is approximated, and the neutron exposure of each third of fuel bundle and control rod are accumulated. The work was reported as a part of the Consumers Research and Development Program.
Date: May 1963
Creator: Barth, N. H.
Object Type: Report
System: The UNT Digital Library
Preliminary Design of a 10-Mw(t) Pebble-Bed Reactor Experiment (open access)

Preliminary Design of a 10-Mw(t) Pebble-Bed Reactor Experiment

The objectives of this study have been to examine the problems of the pebble-bed reactor concept and to conceive a design of a facility for investigating the feasibility of this type of reactor. The design must provide for adequate leaktightness of the contaminated-gas system and adequate maintenance of contaminated components, the most vital feasibility questions of the concept.
Date: May 8, 1961
Creator: Fraas, A. P.; Carlsmith, R. S. & Corum, J. M.
Object Type: Report
System: The UNT Digital Library
Design Study of a Pebble-Bed Reactor Power Plant (open access)

Design Study of a Pebble-Bed Reactor Power Plant

Sanderson & Porter have carried out a series of studies over the last four years which indicate that the pebble-bed reactor way be an attractive way to obtain low-cost power. At the request of the Atomic Energy Commission, two design studies have been carried out on this concept at the Oak Ridge National Laboratory. The first of these a preliminary design of a 10-Mw(t) reactor experiment, the PRRE, was initiated September 10, and a report on the study was issued November 1960. The second phase of the work, a conceptual design study of a 330-Mw (e) central station, was initiated November 1, and is the subject of this report.
Date: May 11, 1961
Creator: Fraas, A. P.; Carlsmith, R. S.; Corum, J. M. & Foster, J.
Object Type: Report
System: The UNT Digital Library
Texas State Securities Board Monthly Bulletin, April 1967 (open access)

Texas State Securities Board Monthly Bulletin, April 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: May 1967
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Texas State Securities Board Monthly Bulletin, April 1966 (open access)

Texas State Securities Board Monthly Bulletin, April 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: May 1966
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders (open access)

Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders

The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas cooled graphite-moderated (GGBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Object Type: Report
System: The UNT Digital Library
Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders. Appendices (open access)

Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders. Appendices

The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Object Type: Report
System: The UNT Digital Library
Preprocessing of Procedure in the ORACLE-Algol Translator (open access)

Preprocessing of Procedure in the ORACLE-Algol Translator

This report describes the preprocessing stage to be added to the present ORACLE-Algol translator which will enable it to translate programs containing procedures. The Algol 60 procedure is an extremely flexible tool, and its full implementation presents a number of difficulties. Since it is undesirable to undertake major revisions of the existing parts of the translator and impossible to solve all of these difficulties in a processing stage, it was necessary to impose certain restrictions on the use of procedures. The result, however, retains the more basic features of the Algol 60 procedure concept. Most of the algorithms published in the Communications of the Association for Computing Machinery can be handled by the preprocessor with few minor or no changes.
Date: May 15, 1961
Creator: Bumgarner, L. L.
Object Type: Report
System: The UNT Digital Library
Monthly Report of Securities Registrations in Texas, April 1962 (open access)

Monthly Report of Securities Registrations in Texas, April 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: May 1962
Creator: Texas. State Securities Board.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History