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in publisher: "North American Aviation"  
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Experimental Determination of the Effect of Reactor Radiation on the Thermal Conductivity of Uranium-Impregnated Graphite

Description: Experiments are described in which the change in thermal conductivity of U-impregnated graphite under neutron irradiation was measured. Thermal resistivities relative to the thermal resistivity of undamaged impregnated graphite are reorted as functions of exposure. From applications of the expermental results to the North American Aviation low-power research reactor the peak tem. of the core is determined for a given reactor power and time of operation.
Date: January 6, 1953
Creator: Hetrick, D. L.; McCarty, W. K.; Steele, G. N.; Brown, M. S.; Clark, E. V.; Holmes, F. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of a Sodium Vapor Compressor Jet for Nuclear Propulsion of Aircraft

Description: Analysis indicates that, in order to achieve supersonic flight with nuclear powered aircraft, a reactor -power plant combination capable of operating at temperatures considerably in excess of current practice must be developed. It is pointed out that there exist two general avenues of approach toward the goal of attaining high temperature reactors and power plants. The first approach involves the continuation and augmentation of research along the lines pursued by the conventional turbo-jet en… more
Date: June 25, 1953
Creator: Schwartz, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fused Fluoride--Inconel System Under Cyclotron Irradiation--Preliminary Results

Description: The fused fluoride-Inconel reactor system was studied under irradiation with nominal 19 Mev deuterons as supplied by the Berkeley 60-inch cyclotron. Chemical, metallographic, magnetic susceptibility, electron diffraction and X-ray diffraction studies were made on the as-received materials, one control run and two irradiated runs. No changes in the fused fluoride fuel were noted. Accelerated intergranular corrosion and increased grain size were observed in the irradiated Inconel specimens. This … more
Date: December 17, 1951
Creator: Goeddel, W.V. & Epp, Jr., A.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Reliability Improvement Program Planning Report for the SNAP 10A Space Nuclear Power Unit

Description: The estimated achieved reliability of SNAP 10A space nuclear power units will be relatively low at the timeof the first SNAPSHOT flight test in April 1963 and the existing R&D program does not provide a significant reliabiity growth thereafter. The total costs of an 8-satellite network using SNAP 10A units over a 5-year period has been approximated for the case where the total cost of a single satellite launched is 8 million dollars.
Date: March 14, 1961
Creator: Coombs, M. G.; Smith, C. K. & Wilson, L. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Role of Ionizztion in Radiatin Annealing

Description: The role of ionization in the phenomenon of" radiation annealing" of graphite has been studied by using a I-MeV electron beam. Changes in the C-axis of a sample with a Hanford irradiation of 460 Mwd/ct were studied. Two thermal anneals of 4 hours each at 350{degree}C proved sufficient to complete the thermal annealing at this temperature. The samples were then irradiated for 7 {1I2} hrs at a temperature of 340 {degree}c. The samples received an irradiation of 47 microampere-hours, equivalent in… more
Date: October 1, 1954
Creator: McClelland, J.D.; Smith, A.W. & Senkovits, E.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SER Temperature Coefficient

Description: Experimentally determine the overall isothermal temperature coefficient of the SER up to the design operating temperatures.
Date: December 31, 1959
Creator: Johnson, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Variation of the magnetic susceptibility of artificial graphite with exposure in the materials testing reactor

Description: The magnetic susceptibility of artificial graphite was determined as a function of exposure in the MTR. Specimens were studied with exposures ranging from 0.07 to 82 {times} 10{sup18} nvt. Fluxes were determined by means of x-ray measurements and resistivity measurements. The dependence of the magnetic susceptibility on exposure in the MTR and also in a Hanford reactor are graphed, and an equivalence factor is calculated.
Date: February 23, 1955
Creator: McCelland, J.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Engineering Test Reactor

Description: A relatively inexpensive reactor for the specific purpose of testing a sub-critical portion of another reactor under conditions that would exist during actual operation is discussed. It is concluded that an engineering tool for reactor development work that bridges the present gap between exponential and criticality experiments and the actual full scale operating reactor is feasible. An example of such a test reactor which would not entail development effort to ut into operation is depicted.
Date: March 16, 1951
Creator: Fahrner, T.; Stoker, R.L. & Thomson, A.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP fuel temperature peaking with cusps in coolant channel

Description: Reactor Fuel Elements--temperature peaking in SNAP due to surrounding rods; systems for nuclear auxiliary power (SNAP)--reactor fuel temperataure peaking due to surrounding fuel rods; temeprature--calculations of peaking of, in SNAP fuel due to sourround fuel rods.
Date: July 19, 1963
Creator: Treuenfels, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shield for Water Boiler

Description: Siimplified shielding calculations indicating the proposed design for the water boiler assembly will reduce the radiation at normal operaton to values well below those which are considered tolerable.
Date: August 8, 1951
Creator: Balent, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Trip Report, Solar aircraft, May 26, 1960

Description: Discussions held with A. S. Stetson, General George Gordes and W. Compton going over technical aspects of Contract NO-S-935 for the research and development studies on coating materials for SNAP reactors.
Date: June 10, 1960
Creator: Henry, D.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Memorandum on Chemical Reactors and Reactor Hazards

Description: Two important problems in the investigation of reactor hazards are the chemical reactivity of various materials employed in reactor construction and the chracteristics of heat transfer under transient conditions, specifically heat transfer when driven by an exponentially increasing heat source (exp t/T). Although these problems are independent of each other, when studied in relation to reactor hazards they may occur in a closely coupled sequence. For example the onset of a dangerous chemical re… more
Date: July 5, 1951
Creator: Mills, M.M.; Pearlman, H.; Ruebsamen, W. & Steele, G., Chrisney, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAPSHOT Safety Program Plan

Description: The SNAPSHOT Safety Program, as described in this document, is therefore formulated to align safety studies performed by separate agencies and their contractors. At the present stage in program development, the plan is principally concerned with the initial SNAPSHOT flight (SNAP 10A). SNAPSHOT represents a special flight mode for the initial reactors operated in space. The flights are designed to permit early space reactor tests prior to resolving all the safety proglems that may be associated … more
Date: June 20, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Data Relating to Hanford Mined Graphite (2273-D) Samples Annealed at NAA

Description: On 2/8/1950, there was mined from process tube 2273 in D pile at Hanford a quantity of graphite power, which was expected to show the most extensive radiation damage of any graphite available at that time. A series of samples of this powder were annealed in 100 degrees increments from 100 degrees to 2000 degrees C at this labaoratory. There were returned to Hanford and shipped by them to the National Bureau of Standards for total stored energy measurements. The present memorandum is comprised o… more
Date: March 15, 1951
Creator: Smith, C. A. & Carter, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Shim Control by Coolant Passage Coating

Description: Work at North American Aviation in connection with the ReactorSafety Program has suggested the use of a poison-bearing "paint" which would coat reactor coolant channels, and provide a supplement to the control systems of the Hanford reactors. A review of Hanford operating problems indicates that this addition to the present control systems would enable an increase in annual production for each reactor of about 6% or the production equivalent of about 21 days at maximum power level. Installati… more
Date: September 17, 1953
Creator: Wheelock, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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