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Office of Scientific & Technical Information Technical Reports
1,189
Technical Report Archive and Image Library
540
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263
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257
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163
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34
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Atomic Energy Commission Reports
206
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121
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69
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60
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12" SODIUM FLOW CONTROLLER. PERMANENT MAGNET COUPLING. MAGNETIC CALCULATION MANUFACTURE AND TEST RESULTS
In order to retain the hermetic feature of the sodium flow controller, magnetic flux linkage of a permanent magnet coupling is used to transmit the torque produced by the operator through the pressure wall. Magnetic calculations, manufacture, and testing of this magnet coupling are described. (M.C.G.)
Date:
August 18, 1961
Creator:
Flator, H.E.
Object Type:
Report
System:
The UNT Digital Library
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
100-C water plant
System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reactor use, 10,000 to 12,000 gpm was demanded by B Area through the 183 BC intertie. The maximum flow that the intertie line could handle, without reducing the filter capacity of the C Area filters, is about 21,000 gpm.
Date:
February 20, 1961
Creator:
Agar, J. D.
Object Type:
Report
System:
The UNT Digital Library
100-K Area Downcomer Test Data Project CGI-883
105-KE downcomer pressure data are tabulated.
Date:
January 10, 1961
Creator:
Hutton, P. H.
Object Type:
Report
System:
The UNT Digital Library
105-C overbore 40 tube test process tube assembly flow and pressure drop calibration test
The object of this test is to determine the hydraulic characteristics of the proposed overbore process tube assembly designs which are to be installed on 105-C reactor for the 40 tube overbore fuel element test.
Date:
July 6, 1961
Creator:
Etheridge, E. L.
Object Type:
Report
System:
The UNT Digital Library
105-C overboring thirteen tube outage, March 6, 1961--March 10, 1961
C Reactor was shut down on a scheduled basis at 8:30 a.m. March 6, 1961 for the purpose of overboring 17 process channels. this report will cover that outage and discuss problems encountered in completing the tasks involved in overboring.
Date:
March 24, 1961
Creator:
Munro, C. A.
Object Type:
Report
System:
The UNT Digital Library
1A HEAT EXCHANGER LEAK TEST. CORE I, SEED 2. Test Evaluation. Section 2
An investigation was conducted to determine which tubes of the 1A loop heat exchanger are leaking. Air pressure and probing tests are inconclusive and cannot be used to verify chemical sampling. (J.R.D.)
Date:
July 24, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
1B HEAT EXCHANGER LEAK TEST. CORE I, SEED 1. Test Results
Descriptions are given of various procedures used in determining leaks in the tubes of the 1B heat exchanger. Air pressurization tests determined leakage and leak rate of nine tubes. The leak-location-detector-probe method was found promising for locating defects along the length of the tube. Results of the probalog, dye-penetrant, and ultrasonic tests proved inconclusive in determining leak locations. (B.O.G.)
Date:
February 24, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
2000 KILOWATT SODIUM TEST FACILITY. Project Description and Progress Reports, June 30, 1958 through September 30, 1959
The design and construction work completed on the 2000-kw Sodium Teat Facility during the period from April 1958 to Oct. 1959 is described. The purpose of the facility project in to test models of equipment components which are to be used in a moltsn plutonium, sodiumcooled fast reactor. (D. L.C.)
Date:
March 1, 1961
Creator:
Whinery, L.A.
Object Type:
Report
System:
The UNT Digital Library
The A.A.E.C. Atmospheric Pressure Heat Transfer Rigs
This technical report describes two atmospheric pressure rigs with associated equipment designed for investigating heat transfer and friction characteristics of different type of "roughened" surfaces to develop suitable surfaces for an H.T.G.C.R. fuel element. Operating details are given together with techniques used to measure heat transfer and friction on a surface assembly incorporating selected "roughened" surfaces. Methods for calculating Stanton numbers, friction factors, and Reynolds numbers for such an assembly are included.
Date:
1961
Creator:
Lawther, K. R. & Draycott, A.
Object Type:
Report
System:
The UNT Digital Library
ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961
Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Date:
October 16, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
ACCEPTOR DOPANTS FOR LEAD TELLURIDE
Alternative P-type dopants such as, Th, P, and As were studied. Ingots were grown from a melt containing one at.% dopant and their electrical properties evaluated. Also, sintered pellets of PbTe were doped by exposure at high temperature to gaseous dopants. In most cases, the doping concentrations obtained were insufficient for SNAP 10A requirements. In the case of As, however, doping of Te-rich PbTe, the desired heavy doping was obtained. These preliminary studies suggest that dopants other than Na might be suitable for SNAP 10A requirements. (auth)
Date:
December 1, 1961
Creator:
McCaldin, J.O.
Object Type:
Report
System:
The UNT Digital Library
Accountability equations for plutonium and tritium yields for PT-IP-305-C at 105-H
It is necessary to provide accountability tables and equations for use in routine product buildup predictions for the duration of the E-N and blanket loads charged under PT-IP-350-C. Recommended values are given.
Date:
May 10, 1961
Creator:
Nechodom, W. S.
Object Type:
Report
System:
The UNT Digital Library
Activity Build-Up Control by High pH Coolant. A Literature Survey
A survey was made of unclassified literature dealing with the control of activity build-up in pressurized water reactors by high-pH coolants. Survey results indicate that a high-pH coolant is desirable for control of induced radioactivity build-up in pressurized water reactors containing significant amounts of stainless steel and that no significant hazards are introduced by adoption of a high-pH coolant. Lithium hydroxide was found to be the most acceptable agent for coolant pH control. Strong-base-form mixed-bed resin is effective in maintaining both coolant pH and coolant purity. (auth)
Date:
January 23, 1961
Creator:
Bergen, C. R.
Object Type:
Report
System:
The UNT Digital Library
Addicks Quadrangle
Topographic map of a portion of Texas from the United States Geological Survey (USGS) project. The map includes towns, historic or notable sites, bodies of water, and other geologic features. Scale 1:24000
Date:
1961
Creator:
Geological Survey (U.S.)
Object Type:
Map
System:
The Portal to Texas History
An Adiabatic Motion Of Charged Particles In Electromagnetic Fields
The guiding center motion and the adiabatic invariants of charged particle trajectories in electromagnetic fields are treated in this review. General and specific theories of charged particle motion are also reviewed.
Date:
January 1961
Creator:
Northrop, Theodore G.
Object Type:
Report
System:
The UNT Digital Library
Adsorption of Krypton and Xenon by Various Materials
The adsorptive capacities of various inorganic adsorbents and activated charcoals for krypton and xenon were determined. Columbia-G activated charcoal had the highest capacity for both krypton and xenon at pressures from 0.01 to 125 mm Hg and temperaturens from 2 to 85 deg C. If a value of 1 is assigned to the capacity of this charcoal at 28 deg C for krypton, other charcoals range from 0.63 to 0.84, molecular sieves (except 4A) from 0.11 to 0.20, and some silica genls from 0.05 to 0.07. Various othenr adsorbennts, including one variety of silica gel and molecular sieve 4A, range from 0.005 to 0.032. Molecular sienve 5A and Columbia-G charcoal adsorbed 11.5 times more xenon than krypton. Adsorption of 7.5% water by either of these adsorbents lowerend their capacity for krypton 25 to 30%, while saturating the sieve material ( approximates 15% H2O) lowered the krypton capacity 80%. (auth)
Date:
December 1, 1961
Creator:
Lloyd, M. H. & McNees, R. A.
Object Type:
Report
System:
The UNT Digital Library
Advanced Engineering Preliminary Program Planning, Rough Draft
The purpose of this document is to assembly certain job elements which may become part of the Advanced Engineerng Subsection programs, so that those individuals who may be requested to participate in such programs may be aware of the nature and form of Advanced Engineering planning.
Date:
April 20, 1961
Creator:
Towle, H.C.
Object Type:
Report
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps
Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
Aerial Radiological Monitoring System: Part 2. Performance, Calibration, and Operational Check-Out of the EG&G ARMS-II Revised System
Report describing "the design, installation, and performance of the Edgerton, Germeshausen & Grier, Inc., Aerial Radiological Monitoring System used in Phase II of the Aerial Radiological Monitoring Survey (ARMS-II)" (p. 5). Contains descriptions and photographs of its components and descriptions of test runs.
Date:
October 1961
Creator:
Hand, J. E.; Guillou, R. B. & Borella, H. M.
Object Type:
Report
System:
The UNT Digital Library
Aerial Radiological Monitoring System: Part 3. Electronic Processing of ARMS-II Data
Report detailing the instrumentation and system performance of the Aerial Radiological Monitoring Survey (ARMS-II), a system used "to perform aerial surveys of ground radioactivity. It supplies both geographical position and radioactivity data in digital form, suitable for use with automatic plotting procedures" (p. 5)
Date:
October 1961
Creator:
Hand, J. E. & Borella, H. M.
Object Type:
Report
System:
The UNT Digital Library
Aeroradioactivity Survey and Areal Geology of the Hanford Plant Area, Washington and Oregon (ARMS-I)
Report regarding an airborne gamma-radioactivity survey that took place over a 9,000 square mile area in south-central Washington and north-central Oregon. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Date:
March 1961
Creator:
Schmidt, Robert George
Object Type:
Report
System:
The UNT Digital Library