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GCRE Critical-Assembly Studies

Description: This report follows critical-assembly studies made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiments.
Date: September 10, 1958
Creator: Dingee, David A.; Ballowe, William C.; Klingensmith, Raymond W.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
Partner: UNT Libraries Government Documents Department
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Stress Analysis of Bulk Effluent System Components in B and C Reactors

Description: This report presents a study of the stresses induced in the elbow and downcomer of the B and C Reactors (bulk effluent systems) by flow momentum and pressurization effects. It is desirable to ascertain the limitations on the bulk outlet temperatures and flow rates from a stress viewpoint; the elbow, top coverplate of downcomer, and top baffle plate being the most severely stressed components.
Date: July 10, 1958
Creator: Adams, O. E., Jr.
Partner: UNT Libraries Government Documents Department
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Bond strength evaluation of the brittle bond problem in production fuel elements

Description: Brittle bonds and the factors controlling their formation have been of substantial concern in the production of dip canned fuel elements. Detection of brittle bonds has been by the chisel test and by metallographic examinations. At best, these are qualitative tests and do not establish the degree of brittleness. For this reason bond tensile strength analysis has been suggested. Tests have been run to determine if a change in canning variables could be detected by a change in bond strength.
Date: November 10, 1958
Creator: Tverberg, J. C.
Partner: UNT Libraries Government Documents Department
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High Temperature Production and Measurement : A Bibliography

Description: The following report is a bibliography containing reports, books and journals on the production of high temperatures (2000-3000 F). The literature provided only covers to the end of 1957.
Date: November 10, 1958
Creator: Frost, Frederick E.
Partner: UNT Libraries Government Documents Department
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Nuclear physics research operation. Monthly report, November 1958

Description: This report is a summary of projects worked on in support of the production reactors at Hanford. The projects include criticality studies, from tasks associated with fuel element reprocessing to shipments of slightly enriched uranium. They include studies of neutron cross sections for different reactions and neutron flux measurements in different reactor locations, as well as design studies for future reactor projects.
Date: December 10, 1958
Creator: Faulkner, J. E.
Partner: UNT Libraries Government Documents Department
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Interim report, Operational physics aspects of supplement A: Production test IP-14-AC, Use of E metal in shield protection

Description: The masonite in the old pile shields is deteriorating because of the temperature conditions to which it is subjected. One method of mitigating this deterioration is to reduce neutron leakage to the shields by utilizing the fringe tubes for target material. One possible target material is depleted uranium, i.e., uranium from which the bulk of the isotope 235 has been removed. The purpose of this test supplement has been to irradiate a fringe depleted pattern to establish the enrichment loading o… more
Date: December 10, 1958
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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A proposal for equitable IPD electrical power cost distribution between areas

Description: Assistance has been requested by Financial Operation to determine the percent of firm and interruptible power used in each area for cost distribution purposes. Also, Power Operations have suggested that the power cost distribution be reviewed. In consideration of these requests, and with the use of improved demand instrumentation within the 151-B, D, and F substations, a proposal for equitable IPD electrical power cost distribution between areas is presented for acceptance or comment by Area Ma… more
Date: July 10, 1958
Creator: Blanchette, V. G.
Partner: UNT Libraries Government Documents Department
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Slug temperature after H{sub 2}O stoppage

Description: On the basis of numerous rough calculations it has generally been assumed that if the water flow to a tube were to stops while pile operation continued. The tube central temperature would increase in a matter of seconds to dangerously high values. In several seconds the water around the central slugs would flash to steam, shortly thereafter the aluminum cans would melt and this would give good contact between the slug and the tube which would quickly melt. The bare uranium would react with the … more
Date: June 10, 1958
Creator: Jones, S. S. & Ekern, W. F.
Partner: UNT Libraries Government Documents Department
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Recent Developments in the Field of the TransplutoniumElements

Description: The author tells about some of the most interesting aspects of recent research on the synthetic transplutonium elements. The amount of recent information on these elements is obviously too much to cover completely in the time that has been placed at my disposal. Therefore, in planning my talk, I have attempted to choose those topics which have the broadest implications for the whole transuranium field of research. Although much important and interesting research is, of course, being done in man… more
Date: September 10, 1958
Creator: Seaborg, Glenn T.
Partner: UNT Libraries Government Documents Department
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Design of an Eddy-Current Brake for a Sodium-Cooled Nuclear Power Reactor

Description: Two eddy-current electromagnets to act as brskes were designed and installed in the sodium-cooled nuclear pcwer reactor SRE to throttle sodium flow throughout the reactor after shutdown in order to maintain a constant reactor temperature gradient. One brake was used on the primary piping system, the other on the secondary system. It was determined that the eddy-current brake should cause a dragging pressure of 0.3 psi at a flow rate of 12 gal/min. The flux density necessary to produce this pres… more
Date: July 10, 1958
Creator: Baker, R. S.
Partner: UNT Libraries Government Documents Department
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Gas Saturated Run on the 400A-1 Pump

Description: A 1585 hr run was completed on the 400A-1 pump with a 0.4 m UC/sub 2/SO/ sub 4/ fuel solution as the pumped fluid, during which it was attempted to operate with gas bubbles in the solution. The gas content ranged from 0.56 ml/gm of solution to 1.189 mi/gm of solution and the gas other than CO/sub 2/, which was assumed to he nitrogen, varied from 0.39 ml/gm of solution to 0.966 ml/gm of solution. Because of uncertainties in the CO/sub 2/ solubility it cannot be stated conclusively that the liqui… more
Date: February 10, 1958
Creator: Payne, H. R.
Partner: UNT Libraries Government Documents Department
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Laboratory and Pilot Plant Evaluation of Stanrock Uranium Concentrate

Description: The laboratory and pilot plant evaluation of Stanrock concentrate is presented. This concentrate meets all FMPC impurity tolerance limits except that for thorium content. The thorium limit can be met by the addition of phosphate as required for thorium-containing uranium concentrates. Laboratory digestion and extraction tests indicate that this material should present no problems in pulse column processing. A pilot plant pulse column test (a test utilizing a modified two-inch-pulse-column syste… more
Date: October 10, 1958
Creator: Leist, N. R.; Hicks, C. T. & Nelli, J. R.
Partner: UNT Libraries Government Documents Department
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A SPHERICAL SHELL LOADED ALONG A LATITUDE CIRCLE

Description: A stress analysis is presented of a spherical shell subjected to a line load acting along a latitude circle in a direction normal to the plane of that circle. (auth)
Date: February 10, 1958
Creator: Greenstreet, B.L.
Partner: UNT Libraries Government Documents Department
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A Flight Study of the Effects of Noise Filtering in the Attack Display on the Pilot's Tracking Performance

Description: Memorandum presenting flight tests conducted with a director-type radar fire-control system, with scope presentation of the steering information, to determine the effects of attack-display smoothing on the pilot's tracking and steering effectiveness in tail-chase and lead-collision beam attacks. Results regarding tail-chase attacks and lead-collision beam attacks are provided.
Date: September 10, 1958
Creator: Turner, Howard L. & Heinle, Donovan R.
Partner: UNT Libraries Government Documents Department
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Wind-Tunnel Investigation at a Mach Number of 2.01 of the Aerodynamic Characteristics in Combined Angles of Attack and Sideslip of Several Hypersonic Missile Configurations with Various Canard Controls

Description: "An investigation of the aerodynamic characteristics of several hypersonic missile configurations with various canard controls for an angle-of-attack range from 0 deg to about 28 deg at sideslip angles of about 0 deg and 4 deg at a Mach number of 2.01 has been made in the Langley 4- by 4-foot supersonic pressure tunnel. The configurations tested were a body alone which had a ratio of length to diameter of 10, the body with a 10 deg flare, the body with cruciform fins of 5 deg or 15 deg apex ang… more
Date: March 10, 1958
Creator: Robinson, Ross B.
Partner: UNT Libraries Government Documents Department
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Some Experimental Heating Data on Convex and Concave Hemispherical Nose Shapes and Hemispherical Depressions on a 30-Degree Blunted Nose Cone

Description: Report discussing heat data obtained on concave and convex hemispherical nose shapes and hemispherical depressions on a blunted 30-degree nose cone at a variety of Mach numbers. Both hot-jet tests and flight tests were carried out.
Date: March 10, 1958
Creator: Hopko, Russell N. & Strass, H. Kurt
Partner: UNT Libraries Government Documents Department
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Free-Flight Investigation of Aerodynamic Heat Transfer to a Simulated Glide-Rocket Shape at Mach Numbers up to 10

Description: "Heat-transfer measurements were made on a simulated glide-rocket shape in free flight at Mach numbers up to 10 and free-stream Reynolds numbers of 2 x 10 based on distance along surface from apex and 3 x 10 based on nominal leading-edge diameter. The model simulated the bottom of a 75 deg delta wing at 80 deg angle of attack. The data indicated that for the test conditions a modified three-dimensional stagnation-point theory will predict to reasonable engineering accuracy the heating on a high… more
Date: September 10, 1958
Creator: Swanson, Andrew G.
Partner: UNT Libraries Government Documents Department
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ESTIMATE OF THE RATIO OF Ta$sup 182$ TO Co$sup 60$ ACTIVITY EXPECTED IN THE APPR-1 CORE

Description: S>Of primary interest in a military reactor is the desirability of quick and easy maintenance of as much of the system as possibie throughout the lifetime of the power plant. It is therefore desirable that no serious amounts of long- lived activity build up in equipment outside the core. An investigation was made to determine the activity due to small amounts of cobalt and tantalum in the stainless steel core of the APPR-1. The investigation indicates that equal weight percentages of Ta and Co … more
Date: February 10, 1958
Creator: Gross, E.E.
Partner: UNT Libraries Government Documents Department
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REACTIVITY OF CERTAIN URANIUM OXIDES WITH ALUMINUM. Terminal Report

Description: The reaction between uranium dioxide and aluminum has been studied at 600 deg C and below. At 600 deg C the visible reaction occurred within a few hours, while, for example, at 500 deg C and below, the specimens had to be at temperature for several days in order to show signs of any reaction. The method of manufacture of uranium dioxide had a pronounced effect on its compatibility. Granulated and high-fired oxides showed lowest, and the steam-treated oxide showed maximum, reactivity. The fact t… more
Date: February 10, 1958
Creator: Eiss, A.L.
Partner: UNT Libraries Government Documents Department
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INTEGRAL FLUX SUPPRESSOR FOR APPR-1, CORE II

Description: An internal flux suppressor will be used for the APPR-1 Core II instead of the external suppressors that are employed in Core I. The reference design of the integral flux suppressor for Core II is as follows: materials Eu/sub 2/O/sub 3/ in stainless steel matrix; compositions 23.2 wt.% Eu/sub 2/O/sub 3/; and dimensions, 0.02 in. x 2.281 in. x 0.875 in. The survey on the cffectiveness of this referencc design has shown that thc peaking of the flux in the control rod fuel element tip is eliminate… more
Date: April 10, 1958
Creator: Leibson, M.J.
Partner: UNT Libraries Government Documents Department
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The Effect of Silicon in the Reprocessing of a Uranium Aluminum Alloy

Description: The insoluble residues produced during the reprocessing of certain nuclear fuel elements containing aluminum, silicon, and uranium were investigated with respect to particle size, shape and distribution, composition, and surface- active tendencies. The fuel material samples studied contained from 0.4 to 7.0% silicon by weight (the high analysis represents a cast base AlSi alloy). The fuel materials were dissolved in mercury-catalyzed nitric acid. Two types of solid residue were produced by actu… more
Date: May 10, 1958
Creator: Parrett, O. W. & Rohde, K. L.
Partner: UNT Libraries Government Documents Department
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