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Office of Scientific & Technical Information Technical Reports
919
Technical Report Archive and Image Library
60
TRAIL Microcard Collection
28
Harris and Eliza Kempner
10
Congressional Research Service Reports
7
John F. Kennedy Memorial Collection
6
John F. Kennedy, Dallas Police Department Collection
6
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Atomic Energy Commission Reports
40
AEC research and development report
17
North American Aviation Reports
10
NYO (Series) (New York)
9
Personal Papers (MS 80-0002)
9
National Bureau of Standards Reports
6
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5
Report (U.S. Atomic Energy Commission)
5
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4
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1,002 Matching Results
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A 1.5 Mwe Thermionic Reactor Space Power System
None
Date:
October 31, 1966
Creator:
Smith, C. K. & Parkinson, R. Y.
System:
The UNT Digital Library
12-INCH SODIUM FLOW CONTROLLER. Technical Manual 20357
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
Creator:
unknown
System:
The UNT Digital Library
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)
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
None
Date:
May 31, 1965
Creator:
unknown
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
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
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
None
Date:
October 31, 1964
Creator:
unknown
System:
The UNT Digital Library
100-N technical manual. Volume 2A: Systems descriptions
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
Creator:
unknown
System:
The UNT Digital Library
I-131 in milk from Cabriolet fallout
None
Date:
March 31, 1966
Creator:
Tamplin, A.
System:
The UNT Digital Library
710 reactor program, progress report No. 13
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
Creator:
unknown
System:
The UNT Digital Library
10th Annual Bio-Assay and Analytical Chemistry Meeting, October 8-9, 1964
None
Date:
October 31, 1966
Creator:
unknown
System:
The UNT Digital Library
1961 Salmon Survey
Explanation of research methods and data collected during a salmon survey at the Project Chariot site near Seattle, Washington.
Date:
October 31, 1965
Creator:
unknown
System:
The UNT Digital Library
909B high energy gull generator
None
Date:
December 31, 1960
Creator:
Stephens, W. H.
System:
The UNT Digital Library
Abstract -- A description of low temperature hydriding of zircaloy at Hanford
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 hydrogen in a totally unexpected and alarming manner. It was found that the downstream few feet of these tubes had a layer of massive hydride platelets, several mils thick, on the inner surface, and that the hydrogen content of the tube wall beneath this layer had increased from the as-fabricated level of 5--15 ppm to 50--75 ppm. The portion of the tubes so affected was downstream of the fuel charge. Physical testing has indicated loss of ductility but no significant changes in strength, Cold burst tests resulted in a ductile failure mode with no tendency toward brittle fracture. A program to determine the basic mechanism responsible for this phenomenon as well as practical means for its elimination will be the subject of …
Date:
March 31, 1966
Creator:
Alexander, W. K.
System:
The UNT Digital Library
Accidental Radiogold (198Au) Liver Scan Overdose With Fatal Outcome
This report addresses the use of radioisotopes for scanning, which has added significantly to the clinician's ability to detect and interpret disease manifestations.
Date:
October 31, 1969
Creator:
Baron, J.M.; Yachnin, S.; Polcyn, R.; Fitch, F.W. & Sturner, W.G.
System:
The UNT Digital Library
Acoustic Noise Tests of Accelerometers and Amplifiers
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.
System:
The UNT Digital Library
Activities of the Cross-Section Compilation and Evaluation Centers at the Brookhaven National Laboratory.
This report addresses the activities of the cross-section compilation and Evaluation Centers at the Brookhaven National Laboratory.
Date:
October 31, 1967
Creator:
Chernick, J.
System:
The UNT Digital Library
Adsorption of Radioactive Gases on Activated Carbon
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.
System:
The UNT Digital Library
Advanced Heat Pipe Thermionic Technology. Task I. Development of High Voltage Module. Mid-Term Status Report, May 1, 1968--February 28, 1969.
This report addresses he design of a heat pipe-thermionic module concept capable of output potentials as high as 28 volts.
Date:
October 31, 1969
Creator:
Longsderff, R.W.
System:
The UNT Digital Library
Advanced Heat Pipe Thermionic Technology. Topical Report for Task Ii. Development of Adsorption Reservoir. Period Covered: May 1, 1968--February 28, 1969.
This report covers work performed on the development of an integral adsorption reservoir thermionic converter.
Date:
October 31, 1969
Creator:
Freggens, R.A.
System:
The UNT Digital Library
Advanced Nuclear Rocket Materials Research
A number of metals, carbides, nitrides, oxides, borides, and uranium gulfides are briefly evaluated concerning their possible applications as advanced nuclear rocket materials. (R.J.S.)
Date:
May 31, 1962
Creator:
unknown
System:
The UNT Digital Library
ADVANCED PLUTONIUM FUELS PROGRAM. Quarterly Status Report, April 1--June 30, 1968, and Second Annual Report, FY 1968
None
Date:
December 31, 1968
Creator:
unknown
System:
The UNT Digital Library
Advanced Plutonium Fuels Program. Quarterly Status Report, January 1-- March 31, 1968
None
Date:
December 31, 1968
Creator:
unknown
System:
The UNT Digital Library
ADVANCED PRESSURE VESSEL MATERIALS.
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 properties and good toughness can be developed. The alloy is structurally stable at long time heating at 425 deg C. Good weldability with filler metal of matching composition was exhibited but weld ductility and toughness are only fair. (F.S.)
Date:
October 31, 1969
Creator:
Robertshaw, F.C.; Stephan, H.R. & McConnelee, J.E.
System:
The UNT Digital Library
Advanced Space Nuclear Power Program. Quarterly Report, 1967, July--September
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
Creator:
unknown
System:
The UNT Digital Library