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6144-Channel Time-of-Flight Analyzer

Description: Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Partner: UNT Libraries Government Documents Department
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Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Description: Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Partner: UNT Libraries Government Documents Department
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Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Description: Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Date: August 1962
Creator: Hanthorn, H. E.
Partner: UNT Libraries Government Documents Department
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Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Description: Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date: August 12, 1960
Creator: Wilburn, N. P.
Partner: UNT Libraries Government Documents Department
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Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Description: Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date: December 9, 1963
Creator: Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
Partner: UNT Libraries Government Documents Department
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The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel

Description: Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2).
Date: October 1964
Creator: Silker, W. B. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department
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Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Description: Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
Date: February 1961
Creator: Pessl, H. J.
Partner: UNT Libraries Government Documents Department
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Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Description: Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date: September 1961
Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
Partner: UNT Libraries Government Documents Department
open access

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
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The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Description: Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
Partner: UNT Libraries Government Documents Department
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The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1

Description: Report regarding an experimental program by Hanford Laboratories' in order "to determine the long-term irradiation behavior of the graphite used as the moderator in N-Reactor. The primary objectives of the program are to provide data for predictions of the distortion of the N-Reactor moderator and the stress conditions which could arise from the difference in the the rate and extent of contraction between the transverse and parallel orientations of the graphite bars" (p. 1).
Date: October 1964
Creator: Helm, J. W.
Partner: UNT Libraries Government Documents Department
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