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12-INCH SODIUM FLOW CONTROLLER. Technical Manual 20357

Description: A manual is presented for the Sodium Flow Controller used in controlling flow to regulate heat transfer in a liquid metal nuclear power plant. A description of the controller, general installation and operational pointers, installation instructions, instructions for dismantling of the Sodium Flow Controller, instructions for assembly of Sodium Flow Controller, list of special tools and fixtures, and repair parts list are given. (M.C.G.)
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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40-MW(e) Prototype High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending June 30, 1962

Description: 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,… more
Date: October 31, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100-N technical manual. Volume 2A: Systems descriptions

Description: This report contains engineering drawings for the control room, reactor monitoring systems, and reactor control systems for the N reactor. Each console in the control room is detailed. Other systems discussed are: stack air monitoring system, charging machine control systems, and heating and ventilation control systems. A N reactor plant glossary is included.
Date: December 31, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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710 reactor program, progress report No. 13

Description: Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design, (DCC)
Date: March 31, 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

1961 Salmon Survey

Description: Explanation of research methods and data collected during a salmon survey at the Project Chariot site near Seattle, Washington.
Date: October 31, 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Abstract -- A description of low temperature hydriding of zircaloy at Hanford

Description: The two K Reactors at the Hanford Plant of the Atomic Energy Commission were retubed in 1963 with ribless Zircaloy process tubes. These tubes, 1.81 inch OD x 0.037 inch wall, were made by tube reducing methods from extruded blooms and were installed without final pickling or autoclaving. These tubes are used with once-through filtered water with a maximum coolant temperature of approximately 110 C. After approximately two years` service, it was discovered that these tubes were absorbing hydroge… more
Date: March 31, 1966
Creator: Alexander, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Acoustic Noise Tests of Accelerometers and Amplifiers

Description: This report describes a series of acoustic noise sensitivity tests which have been run on accelerometer amplifiers. The test specimens consists of NRX-A1 type components and two additional piezoelectric accelerometers which are being considered for possible application in radiation environments.
Date: July 31, 1964
Creator: Loftus, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Adsorption of Radioactive Gases on Activated Carbon

Description: The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Date: August 31, 1960
Creator: Madey, Richard; Barker, J. J.; Beebe, M. R. & Stephenson, T. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced Pressure Vessel Materials.

Description: Data on 5Cr - 3Mo - 12Ni alloy, PH13 - 8Mo and Iconel 718 for pressure vessel application are given. The 5Cr - 3Mo - 12Ni posseses characteristics suited to uniform aging of heavy sections. Tensile and toughness properties are good, and structural stability up to 315 deg C is adequate. Weldability with 12Ni - 3Cr - 3Mo filler material is good but 12Ni - 5Cr - 3Mo filler is more efficient. Aging characteristics of PH13 - 8Mo may not be suited to uniform aging of heavy sections. Excellent tensile… more
Date: October 31, 1969
Creator: Robertshaw, F. C.; Stephan, H. R. & McConnelee, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced Space Nuclear Power Program. Quarterly Report, 1967, July--September

Description: This report descriptively talks about the advanced space nuclear power program. Starting with the 1967 third- quarter report, each quarterly report of the Advanced Space Nuclear Power Program is published in two parts. The first contains unclassified material only, the second contains classified material only.
Date: October 31, 1968
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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