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Niobium Phase Diagrams

Description: The following report is the final technical report on a series of reports under contract AT(11-1)-515, titled "Niobium Phase Diagrams", covering the period from April 15, 1957 to April 16, 1960.
Date: May 15, 1960
Creator: Elliott, Rodney P. & Komjathy, Steven
Partner: UNT Libraries Government Documents Department
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Magnetic Recorder for Nuclear Pulse Application : Covering the Period from February 6, 1960 to April 5, 1960

Description: Abstract: "The accuracies which can be achieved in analog recording systems are for the most part tape limited. While reasonable variations in tape speed do not directly affect the accuracy, such variations result in improper tape tensioning, which in turn results in poor head-to-tape contact. The quality of the tape transport mechanism should be such that the error introduced by improper head- to tape contact is less than tape errors. Some additional equipment is necessary in setting up a tape… more
Date: April 15, 1960
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
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An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
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A Multichannel Digital Recording System

Description: Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date: September 15, 1960
Creator: Truitt, R. W.
Partner: UNT Libraries Government Documents Department
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Thermal Cycling Tests of Porous Uranium

Description: Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date: March 15, 1960
Creator: Wilkinson, L. E.
Partner: UNT Libraries Government Documents Department
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Zircaloy-4 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-4 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Studies of Reactor Containment : Monthly Technical Progress Report No. 32

Description: The report covers work performed during the period December 1, 1959 through December 31, 1959. The general objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation of methods of reducing that loading, and the study of the response of and design criteria for external contai… more
Date: January 15, 1960
Creator: Zaker, T. A. (Thomas Allen)
Partner: UNT Libraries Government Documents Department
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Reactor Grade Zircaloy-2 Ingot

Description: Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-2, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Wire Material

Description: Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Sheet and Strip Material

Description: Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Steady-State Tests of a Reactor Safety Device

Description: Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
Date: December 15, 1960
Creator: Springer, T. H.
Partner: UNT Libraries Government Documents Department
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A Device for Continuous Detection of Hydrogen in Sodium

Description: Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date: December 15, 1960
Creator: Strahl, H.
Partner: UNT Libraries Government Documents Department
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Utilization of Radiactive Isotpoes in Coal Process Research Quarterly Status Report: May-July 1960

Description: "This is the first quarterly report on Task II of the subject Utilization of Radioactive Isotopes in Coal Process Research. There were two separate projects on Tank I; I. methods Development for Tritium Labeling of Coal Product Hydro-carbons, and II. Applications of Radio-Tracer Techniques to the Study of Fluidized Particle Mechanics. The following extended work on Task II concerns only Methods Development of Radio-Tracing With Tritium."
Date: August 15, 1960
Creator: Yavorsky, P. M. & Gorin, E.
Partner: UNT Libraries Government Documents Department
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Significance of operating experience with poison splines at KE Reactor

Description: The demonstrated operating efficiency performance which has resulted from poison spline usage forces an economic decision concerning the self-supported and bumper fuel element programs. As originally conceived the projection fuel elements would preclude the insertion of a spline under the fuel charge; thus it is very important that means be devised either to make poison spline usage compatible with future pile loadings or to demonstrate that some other supplementary control system, which is com… more
Date: July 15, 1960
Creator: Franklin, F. C.
Partner: UNT Libraries Government Documents Department
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Reactor, Plant Engineering short-range program in support of reactor operating continuity

Description: Reactor maintenance problems and engineering studies have identified various reactor rear face piping problems at 105-B, D, DR, F, and H. The long-range solutions to these problems are outlined in classified document HW-65269, ``Existing Reactor Rear Face Piping Review.`` These problems, however, must also be considered from the short-range view to minimize their effects on continuity of reactor operation during the interim until the permanent remedy can be accomplished. This is expected to be … more
Date: September 15, 1960
Creator: Hutton, P. H.
Partner: UNT Libraries Government Documents Department
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In-reactor rupture testing of Zircaloy-2 clad seven-rod cluster fuel elements

Description: Three tests have been run in the ETR in high temperature, high pressure, recirculating water. In one test, previously unirradiated fuel elements were used and in the other two the fuel was irradiated to 2400 MWD/T at HAPO prior to insertion in the ETR. Failure was initiated by shearing off a projection on the surface of one rod of a fuel element, thus opening a 25-mil hole through the cladding. The projection was sheared off by a hydraulically operated chisel controlled from outside the reactor… more
Date: April 15, 1960
Creator: Call, R. L. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
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Production test IP-314-A measurement of fuel element temperature change as the result of film deposition

Description: The objective of this production test is to measure deposition on fuel element temperatures during irradiation in high pH water. A Zircaloy-2 jacketed natural uranium solid cylindrical fuel element with thermocouples located at various positions in the element and adjacent coolant channel will be irradiated in the KER Loops to measure the effect of crud film buildup on fuel temperature. Two 1.82 by 1.45 inch enriched 36 inch long tubular elements will be used to provide enough heat to permit op… more
Date: April 15, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Gamma activity of irradiated zircalloy samples

Description: Three small samples of zircalloy-2, obtained from a KER tube, were irradiated in the Quickie Facility in F Reactor for one, four, and nine months, respectively. Each sample weighed approximately two grams. One day after discharge from the reactor, the specific activity of each of the samples was essentially the same (about 150 mr/hr/gram at one foot in air). Attenuation measurements taken one day after discharge using lead plates yielded a ten-fold reduction in gamma intensity for each 0.95 inc… more
Date: June 15, 1960
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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Fuel element study for Reactor Overbore Program

Description: Recent studies have confirmed that large incentives exist for overboring the reactor process channels approximately 500 mils in the C and five old reactors under the proposed Plant Improvement Program. Conservative estimates of the incentives for overboring indicate a payout period of about two years for the proposed work, an increase in plutonium production of 15--18%, derived from increased conversion ratio and a reduction in plant unit cost. Since sufficient progress has been made in the are… more
Date: December 15, 1960
Creator: Stringer, J. T. & Blanton, W. A.
Partner: UNT Libraries Government Documents Department
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Optimization of K Reactor power levels related to a zirconium tube replacement project

Description: The assumption of tube replacement losses can have a significant effect in the determination of optimum power levels and goal exposures. The tube replacement loss term in the reactor process optimization model is based on calculating the average projected tube replacement losses that will result from operation at given power and temperature conditions. Tube replacement losses associated with external corrosion, Van Stone flange failure, etc. (i.e., basically non-power level-temperature dependen… more
Date: November 15, 1960
Creator: Fuller, N. E. & Graves, S. M.
Partner: UNT Libraries Government Documents Department
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Cap-spire pulsing

Description: The cap-spire pulsing technique of preheating the cap-spire portion of the fuel assembly does significantly improve the brazing of the cap-spire assembly. The air pocket at the spire wafer junction is fully removed. The cap side wafer is essentially 100% wetted with brazing alloy. Destructive tests show that a 4 to 1 improvement in most quality measurements is achieved over present cap preheating techniques, without using additional cleaning step of spire etching. The pulsing is accomplished by… more
Date: June 15, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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