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Hazards Analysis of the Organic Moderated Reactor Experiment

Description: Introduction: The description of the Organic Moderated Reactor Experiment, (OMRE), its location, its safety system, and operative procedures have been previously detailed. The present report, although dealing with the subject of OMRE safety, has the more detailed intent of (1) determining the behavior of the OMRE under extremely unlikely sets of conditions; and (2) providing additional design information in the areas of reactivity coefficients, burnout heat flux, and reactor control.
Date: December 15, 1959
Creator: Williams, R. O., Jr.; Allen, W. O.; Ash, E. B.; Scott, W. W.; Shimazaki, T. T.; Sletten, H. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mounting Thermocouples on SPERT Test Assemblies

Description: Technical report. From Abstract: "A method of fastening thermocouples to 0.030-inch-thick aluminum cladding on test fuel elements was developed. The installation does not lead to hot spots by the addition of extra metal of the distortion of the cooling water channels. Fuel element temperatures were faithfully followed in SPERT tests up to the melting point. The method has been useful for fastening thermocouples to aluminum sections in general."
Date: December 1959
Creator: Sanders, Harold S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient Flow Performance in a Multi-Loop Nuclear Reactor System

Description: The method present can be used to determine fluid flow and coolant pump speed transients in a nuclear reactor system. Included are transients due to power failure, starting pumps in idle loops, and the opening of an active pump's discharge. Parallel pumps in the system may be analysed independently of each other. Typical cases are presented for the N.S. Savannah (NMSR) and Consolidated Edison Thorium Reactor (CETR).
Date: December 1959
Creator: Boyd, George M., Jr.; Rosser, Ralph M. & Cardwell, Bennett B., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SM-2 Critical Experiments : CE-1

Description: Abstract: Critical experiment studies were performed, varying the parameters U235, B10 and metal to water ratio, in the SM-2 7 x 7 core configuration with 38 stationary elements and seven control rods of the SM-1 (APPR-1) type. An experimental mock-up of the SM-1 was assembled using the basic SM-2 fuel plates. Excellent agreement between the SM-1 boron loading, determined by chemical analysis, and the SM-1 mock-up boron loading, for equivalent bank positions, was noted. Several SM-2 mock-ups, … more
Date: November 30, 1959
Creator: Noaks, J. W.; McCool, W. J.; Robinson, R. A.; Schrader, E. W. & Weiss, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SRE Fuel Element Damage: An Interim Report

Description: Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date: November 30, 1959
Creator: Jarrett, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Terminal Status Report for the Processing Refabrication Experiment

Description: Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
Date: November 15, 1959
Creator: Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Meeting: September 1959

Description: From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.
Date: November 3, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lynchburg Test Reactor: Critical Experiment, Hazard Evaluation

Description: This report summarizes the hazards associated with the operation of the Lynchburg Test Reactor (LTR) critical experiments. The LTR critical experiment program is outlined and the design of the experiment is described. The experiments will provide basic data to check two-dimensional calculational methods and provide information needed in the design of the LTR.
Date: November 1959
Creator: Engelder, T. C. & Schutt, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Oxidation of Neptunium(V) by Vanadium(V)

Description: Technical report. From Abstract: "Rate data are presented for the oxidation of neptunium (V) by vanadium (V) in nitric acid." From Summary: "Rates of oxidation of neptunium (V) were determined by a solvent extraction technique based on the difference in distribution coefficients for neptunium (V) and neptunium (VI)."
Date: November 1959
Creator: Dukes, Ernest K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Np237 and Pu238 From Irradiated Neptunium Oxide

Description: Technical report. From Abstract: "An ion exchange process was demonstrated for the recovery of Pu238 from irradiated neptunium oxide. Three cycles of anion exchange proved adequate for the removal of fission products and for the separation of the neptunium and plutonium from each other."
Date: November 1959
Creator: Burney, Glenn A. & Prohaska, Charles A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ultrasonic Energy Applied to Aluminum Extrusion Cladding of Tubes

Description: Technical report. From Abstract: "Ultrasonic energy appropriately applied to the die or container of a laboratory-type direct extrusion press effected a marked increase in the free extrusion rate of lead and aluminum billets at a constant extrusion rate. the same results were obtained in extrusion cladding steel tubes with aluminum. Rate increases were generally 100 per cent or greater, and decreases in force were usually within the range of 10 to 20 per cent. Furthermore, the shape and slope o… more
Date: November 1959
Creator: Jones, J. Byron; DePrisco, Carmine F.; Maropis, Nicholas & Thomas, John G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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