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Residual Stresses in Extruded Graphite Tubes
None
Date:
January 10, 1964
Creator:
Price, R. J.
System:
The UNT Digital Library
Experimental techniques used for high-temperature, vacuum irradiations of electrical components and materials
None
Date:
October 10, 1964
Creator:
Basham, S. J.; Rieder, W. G.; Stang, J. H.; Gruber, H. T. & Fairand, B. P.
System:
The UNT Digital Library
Mound Laboratory Progress Report for April 1964
None
Date:
July 10, 1964
Creator:
Eichelberger, J. F.; Grove, G. R. & Jones, L. V.
System:
The UNT Digital Library
Electrical irradiation test 23/L501 pressure transducers: final test report 1.9.5-2E. Volume II
None
Date:
April 10, 1964
Creator:
Robb, T.C.
System:
The UNT Digital Library
Geometrical and Attenuation Corrections for a Two Crystal Whole-Body Counter Body Scanning With an 8 X 4-Inch Sodium Iodide Crystal. Final Report
None
Date:
March 10, 1964
Creator:
Hine, G. J.; Genna, S. & Burrows, B. A.
System:
The UNT Digital Library
Design of a Cryogenic Two Point Liquid Level Controller
This report presents a design of a two-point liquid level controller for cryogenic liquids in the range of 7°R (liquid helium) to 160° (liquid oxygen) that uses carbon composition resistors for the sensing elements.
Date:
March 10, 1964
Creator:
Henson, C.A.
System:
The UNT Digital Library
Experimental determination of the variation in flow parameters for crowned and straight spline couplings
None
Date:
August 10, 1964
Creator:
Jacob, W.L.
System:
The UNT Digital Library
Development of Plutonium-Bearing Fuel Materials. Monthly Progress Letter, January 1964
During this period, continued effort has been placed on the fabrication of high burnup irradiation test specimens, on additional UO2-PuO2 and PuO2 sintering, on oxygen diffusion and thermal expansivity measurements using UO2-PuO2, and on the preparation of reproducible PuO2 powder.
Date:
February 10, 1964
Creator:
Puechl, K. H.
System:
The UNT Digital Library
Development of Plutonium-Bearing Fuel Materials. Monthly Progress Letter for February 1964
During this period, plutonium wire was extruded and three crystal growing tests were performed in the modified Andrade apparatus. In addition, continued effort has been placed on the fabrication of the high burnup irradiation test specimens, on additional UO2-PuO2 sintering studies and on oxygen diffusion and thermal expansivity measurements.
Date:
March 10, 1964
Creator:
Puechl, K. H.
System:
The UNT Digital Library
PATHFINDER ATOMIC POWER PLANT. RECIRCULATION PIPING DESIGN
The coolant recirculation system in the Pathfinder reactor comprises three mixed-flow centrifugal pumps and three piping loops. The design criteria are summarized; and flexibility and stress analyses on the piping are presented, together with a vibration analysis of one pump and loop. The results indicate that vibration should be no problem, that all stresses are within the allowable limits, and that there should be no resonance difficulties during pump operation. (D.C.W.)
Date:
January 10, 1964
Creator:
Nolan, D. J. & Patterson, J. F.
System:
The UNT Digital Library
Consolidated Controls Corporation LVDT Pressure Transducers Models 413M35 and 412M102
Consolidated Controls Corporation (CCC)* LVDT Pressure Transducers, Models 416M35 and 412M102, were analyzed to determine their expected performance in a radiation fields.
Date:
March 10, 1964
Creator:
Fluke, G. L.
System:
The UNT Digital Library
DEMONSTRATION DISPOSAL OF HIGH-LEVEL RADIOACTIVE SOLIDS IN LYONS, KANSAS, SALT MINE: BACKGROUND AND PRELIMINARY DESIGN OF EXPERIMENTAL ASPECTS
A demonstration of the disposal of high-level radioactive waste solids to be carried out in a salt mine at Lyons, Kansas, will have as its objectives: (1) the demonstration of required waste-handling equipment and techniques, (2) the determination of the stability of salt under the influence of heat and radiation, and (3) the collection of information on creep and plastic flow of salt which is needed for the design of an actual disposal facility. As presently conceived, 14 irradiated fuel assemblies from the Engineering Test Reactor will serve as a source of radiation in lieu of actual solidified wastes. The assemblies will be placed in a circular array of holes in the floor with one can in the center and other six cans located peripherally, spaced 5 ft on centers. During the course of the 2-year test, four sets of assemblies will be used to achieve a peak dose to the salt of about 8 x 10/sup 8/ rad and the temperature of the adjacent salt will be maintained at 200 deg C with electrical heaters. A second array, consisting only of heaters, will be operated as a control to determine those effects due solely to heat. In addition to …
Date:
January 10, 1964
Creator:
Bradshaw, R. L.; Perona, J. J. & Blomeke, J. O.
System:
The UNT Digital Library