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323,261 Matching Results

Start Over Decade 1960-1969

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prev Results: 73 - 96 of 323,261 next
Best Match Title Creator Date Created (Newest) Date Created (Oldest) Date Added (Newest) Date Added (Oldest)
E-23 at Station 2 (Nov.1963)

E-23 at Station 2 (Nov.1963)

Photograph of Norman FD E-23 pump panel. Located at station 2.
Date: November 1963
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History
A 23-Group Neutron Thermalization Cross Section Library (open access)

A 23-Group Neutron Thermalization Cross Section Library

A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)
Date: July 15, 1963
Creator: Doctor, R. D. & Boling, M. A.
Object Type: Report
System: The UNT Digital Library
E-23 hose bed (Nov. 1963)

E-23 hose bed (Nov. 1963)

Photograph of Norman FD E-23 hose bed. Photo taken at station 2.
Date: November 1963
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History
The 25-Inch Liquid Hydrogen Bubble Chamber (open access)

The 25-Inch Liquid Hydrogen Bubble Chamber

None
Date: May 25, 1964
Creator: Barrera, F.; Byrns, R. A.; Eckman, G. J.; Hernandez, H. P.; Norgren, D. U.; Shand, A. J. et al.
Object Type: Report
System: The UNT Digital Library
25 Year Service Award to Mr. Lobrecht

25 Year Service Award to Mr. Lobrecht

Photograph of Mr. Tidwell presenting Mr. Lobrecht with a 25 year Service Award.
Date: August 22, 1969
Creator: Kilpatrick, Lynn
Object Type: Photograph
System: The Gateway to Oklahoma History
[$29.88 price slide]

[$29.88 price slide]

Photograph of a slide with the price "$29.88."
Date: 1961
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Photograph
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System

Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Date: January 31, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis

Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
Date: February 28, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
30 Year Service Award to Mr. Leonard

30 Year Service Award to Mr. Leonard

Photograph of Mr. Tidwell presenting Mr. Leonard with a 30 year service award.
Date: August 22, 1967
Creator: Kilpatrick, Lynn
Object Type: Photograph
System: The Gateway to Oklahoma History
30 Year Service Award to Mr. Milton

30 Year Service Award to Mr. Milton

Photograph of Mr. Tidwell presenting Willis Milton with a 30 year Service Award.
Date: August 22, 1969
Creator: Kilpatrick, Lynn
Object Type: Photograph
System: The Gateway to Oklahoma History
30 Year Service Award to Mr. Stidham

30 Year Service Award to Mr. Stidham

Photograph of Mr. Tidwell presenting Mr. Stidham with a 30 year service award.
Date: August 22, 1967
Creator: Kilpatrick, Lynn
Object Type: Photograph
System: The Gateway to Oklahoma History
31 Men With Vision (open access)

31 Men With Vision

The booklet contains a brief history of Denton County National Bank's conception and first seventy-five years of operation, including photographs of the thirty-one men who petitioned the Treasury Department in Washington, D.C. for the right to form a national bank in 1892.
Date: 1967-01~
Creator: Drenner, William E.
Object Type: Pamphlet
System: The Portal to Texas History
[35 mm film processing machine]

[35 mm film processing machine]

Photograph of a 35 mm film processor machine.
Date: 1967
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Photograph
System: The UNT Digital Library
[35 mm film processor]

[35 mm film processor]

Photograph of 35 mm film processor machine.
Date: 1967
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Photograph
System: The UNT Digital Library
40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Quarterly Progress Report for the Period Ending April 30, 1965 (open access)

40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Quarterly Progress Report for the Period Ending April 30, 1965

None
Date: May 31, 1965
Creator: unknown
Object Type: Report
System: The UNT Digital Library
40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Summary Progress Report for the Period Ending, October 1964 (open access)

40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Summary Progress Report for the Period Ending, October 1964

None
Date: December 15, 1964
Creator: unknown
Object Type: Report
System: The UNT Digital Library
40-MW(e) Prototype High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending June 30, 1962 (open access)

40-MW(e) Prototype High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending June 30, 1962

Research and development progress specifically directed toward the construction of a 40-Mw(e) prototype power plant employing a high-temperature, gas-cooled, graphitemoderated reactor known as the HTGR is reported. Irradiation of element III-B in the in-pile loop continued satisfactorily. The element has generated a total of l36.3 Mw-hr of fission heat. The gross activity in the purge stream increased slightly to about 350 mu C/cm/sup 3/. By taking larger gas samples than were previously taken, a value of 0.02 VC/cm/sup 3/ was obtained for the gross activity of the primary loop. Element III-A, which was removed from the loop after generating 133 Mw-hr of fission heat, was disassembled and examined. No fuel-compact damage of any type was visible. Determination of the distribution of fission products in the element is under way, Fissionproduct- release data for in-pile-loop element III-A were calculated. During the 133 Mw- hr of operation, the release fraction increased by approximately one order of magnitude. Also calculated were the xenon and krypton release data for the first 100 Mw-hr of III-B operation. The release rate for the longer-lived isotopes increased bv about a factor of 10 and that of the shorter-lived isotopes by about a factor of 100. A test …
Date: October 31, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
40-Mw(E) Prototype High-Temperature Gas-Cooled Reactor. Research and Development Program. Quarterly Progress Report for the Period Ending March 31, 1963 (open access)

40-Mw(E) Prototype High-Temperature Gas-Cooled Reactor. Research and Development Program. Quarterly Progress Report for the Period Ending March 31, 1963

None
Date: October 31, 1964
Creator: unknown
Object Type: Report
System: The UNT Digital Library
40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959 (open access)

40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959

The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading of the reactor were improved by important advances in methods of fabrication and testing of both fuel compacts and graphite sleeves. The hot-pressing process for making fuel compacts was used successfully to make full-size compacts with a uniform distribution of ThC/sub 2/- UC/sub 2/ particles. Three irradiation capsules were fabricated and inserted in a test reactor to determine fuel compact and sleeve performance under HTGR conditions of irradiation and temperature. Two of these ran satisfactorily for the scheduled time of operation. A scope design study of the in-pile loop that will be used to evaluate the full-diameter graphite-clad element was completed. Experiments to determine the extent of fuel migration within the element were undertaken. Preliminary results …
Date: September 1, 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
40-MW(E) PROTOTYPE HIGHTEMPERATURE GAS-COOLED REACTOR. POST CONSTRUCTION RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for Period Ending January 31, 1965 (open access)

40-MW(E) PROTOTYPE HIGHTEMPERATURE GAS-COOLED REACTOR. POST CONSTRUCTION RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for Period Ending January 31, 1965

None
Date: February 26, 1965
Creator: unknown
Object Type: Report
System: The UNT Digital Library
40-tube overbore facility location, C Reactor (open access)

40-tube overbore facility location, C Reactor

Possible locations of the projected 40-tube overbore facility at the C Reactor are discussed from the standpoint of obtaining conversion ratio data applicable to a full-reactor overbore program.
Date: April 19, 1961
Creator: Nilson, R.: Nechodom, W. S.
Object Type: Report
System: The UNT Digital Library
50 B Complex

50 B Complex

Photograph of the 50 B Comples-mixed clay and loams range site. Excellent condition, moderate utilization. Claypen on left, loamy on right.
Date: July 14, 1960
Creator: Fry, Chester
Object Type: Photograph
System: The Gateway to Oklahoma History
E-58 (1968)

E-58 (1968)

Photograph of Weatherford Engine 58 in the OSFA parade in Clinton.
Date: 1968
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History