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Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the r… more
Date: February 15, 1961
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium

Description: Graphs for estimation of plutonium and trans-plutonium isotopic content of irradiated plutonium reactor fuel of various initial isotopic compositions.
Date: December 15, 1958
Creator: Brauer, F. P. & Burley, Helen H.
Partner: UNT Libraries Government Documents Department
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Construction Completion Report: CAI-816, 100-N Reactor Plant

Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
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Comparative Study of PuC-UC and PuO₂-UO₂ as Fast Reactor Fuel

Description: From abstract: "This section, Part II, extends the comparison of two ceramic fuel systems to include the fuel cycle cost comparison in greater detail particularly with respect to fabrication and reprocessing unit costs."
Date: November 15, 1962
Creator: Collins, G. D.
Partner: UNT Libraries Government Documents Department
open access

Experimental Studies of Transient Effects in Fast Reactor Fuels

Description: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F.… more
Date: November 15, 1962
Creator: Field, J. H.
Partner: UNT Libraries Government Documents Department
open access

Plating Thickness Tester

Description: An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.
Date: November 15, 1957
Creator: Fitch, C. E., Jr.
Partner: UNT Libraries Government Documents Department
open access

Design Study: Sodium Modular Reactor

Description: This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
open access

A Versatile Spectrometer Magnet Power Supply

Description: Early results from actual laboratory operation of a more versatile magnet supply.
Date: April 15, 1963
Creator: Groppe, W. A.
Partner: UNT Libraries Government Documents Department
open access

Ultrasonic Resin Level Detector

Description: This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
Partner: UNT Libraries Government Documents Department
open access

Critical Mass Studies of Plutonium Solutions

Description: Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
Partner: UNT Libraries Government Documents Department
open access

Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1

Description: Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Date: March 15, 1960
Creator: Millhollen, M. K.
Partner: UNT Libraries Government Documents Department
open access

A Sequence for Predicting Waste Transport by Ground Water

Description: From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
Partner: UNT Libraries Government Documents Department
open access

Zero Power Experiments for the SM-1 Core II : Task XV

Description: Abstract: An element by element reactivity check for SM-1 Core II fuel elements and control rod absorber sections was performed and the burnable nuclear poison loading in the SM-1 Core II stationary fuel elements was established. An approach to criticality of the SM-1 Core II was performed by the inverse multiplication method and the critical rod bank position obtained as a function of fuel loading up to the full SM-1 Core II loading. Maximum and minimum core reactivity measurements were obtai… more
Date: March 15, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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