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Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments

Description: From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date: July 1963
Creator: Comprelli, F. A.; MacMillan, D. F. & Spalaris, C. N.
Partner: UNT Libraries Government Documents Department
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The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results

Description: From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date: July 12, 1963
Creator: Zelezny, W. F.
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Reactor Project Semiannual Progress Report: March 1964

Description: Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
Date: July 1964
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Fuel Core Tester - UT-2

Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Partner: UNT Libraries Government Documents Department
open access

Hanford Controlled Potential Coulometer

Description: Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date: July 11, 1960
Creator: Connally, R. E. & Scott, F. A.
Partner: UNT Libraries Government Documents Department
open access

The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Description: Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date: July 1961
Creator: Triplett, J. R.; Merrill, E. T. & Burr, J. R.
Partner: UNT Libraries Government Documents Department
open access

The Hanford Isotopes Production Plant Engineering Study

Description: Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Date: July 1963
Creator: La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.
Partner: UNT Libraries Government Documents Department
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