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High Flux Isotope Reactor: a General Description

Description: Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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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
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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
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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
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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
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Graphite burnout, interim report on IP-25-A (PT-105-532-E)

Description: Graphite reacts with such gases as CO{sub 2}, O{sub 2}, or water vapor to form gaseous oxides of carbon. In the case of CO{sub 2}-graphite interaction, the reaction rate is not significant until about 550 C. Water oxidizes graphite, very roughly, three times faster than CO{sub 2}. Air will oxidize graphite appreciably at temperatures below 500 C. Graphite removal from Hanford reactors is very important, since graphite is used both as a structural support and a moderator for neutrons. Griggs has… more
Date: March 15, 1960
Creator: Ryan, B. A. & de Halas, D. R.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

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
open access

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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SYNTHESIS AND FABRICATION OF REFRACTORY URANIUM COMPOUNDS. Quarterly Report No. 5, August 1 through October 31, 1960

Description: Additional quantities of UC, UN, and U/sub 3/Si/sup 2/ were prepared to be used in fabrication of test specimens for property determinations. A reduction in oxygen contamination of UN and U/sub 3/Si/sup 2/as achieved by improved techniques of synthesis.>s Preliminary values for thermal expansion, modulus of elasticity, and corrosion in boiling water were also obtained for these materials. (For preceding period see TID-6591.) (J.R.D.)
Date: November 15, 1960
Creator: Taylor, K. M. & McMurtry, C. H.
Partner: UNT Libraries Government Documents Department
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Protection of Graphite by Impregnation. Quarterly Progress Report No. 3 for September 1-November 30, 1960. Vitro Job 2195

Description: The hypothesis that sample resistivity is the controlling factor in electrokinetic impregnation was substantiated. Experiments show that dense clay- bonded silicon carbide can be impregnated beneath the surface pores whereas only surface pore impregnation is achieved with both dense and porous graphite. The resistivity of the materials differ by a factor of about 1O/sup 10/. Although deep penetration of the substrate by the particles of the coating system is not achieved during deposition, ther… more
Date: December 15, 1960
Creator: Ortner, M. H. & Klach, S. J.
Partner: UNT Libraries Government Documents Department
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A Study of Sodium Fires

Description: A study of sodium fires was performed to obtain detailed information on their characteristics and behavior in order to develop techniques for preventing, containing, and combatting them. lnvestigation was made of the technology of sodium fires, design criteria for improving the fire resistance of equipment and installations using sodium as a coolant, extinguishing materials and procedures for fighting sodium fires, and the evaluation of protective equipment. (auth)
Date: October 15, 1960
Creator: Gracie, J. D. & Droher, J. J.
Partner: UNT Libraries Government Documents Department
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Gas Diffusion Into a Bubble of Fixed Radius

Description: The problem of radiolytic gas diffusion into a bubble of fixed radius is solved. A constant source of radiolytic gas is assumed. The concentration of gas at the bubble surface is related to the pressure within the bubble by Henry's constant. (W. L.H.)
Date: July 15, 1960
Creator: Warner, C., III
Partner: UNT Libraries Government Documents Department
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Metallurgy of Zircaloy-2. Part I. The Effects of Fabrication Variables on the Anisotropy of Mechanical Properties

Description: The anisotropy of mechanical propertles of Zircaloy-2 was studied as a function of fabricatlon variables. The variatlon in tensile and impact properties with specimen orientation was taken as the measure of the anisotropy of mechanical properties for each material. A qualitative separatlon of the effects of the fabrication variables on the resulting anisotropy of mechanical properties is made, but it is valid only in the rolling plane of the plate. A contractile strain ratio, a ratio of the nat… more
Date: November 15, 1960
Creator: Rittenhouse, P.L. & Picklesimer, M.L.
Partner: UNT Libraries Government Documents Department
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Experimental and Research Work in Neutron Dosimetry. Final Summary Report for the Period May 15, 1959-June 15, 1960

Description: A practical, prototype silicon p-n junction fast-neutron dosimeter, sensitive in the same range as human tissue, was developed, together with sn associated read-out circuit to facilitate the accurate measurement of accumulated dose. From both theoretical and experimental considerations, it was demonstrated that the dosimeter is essentially insensitive to the gamma and thermal components of a uranium fission spectrum. It was shown that accumulated damage effects appear to be environmentally stab… more
Date: June 15, 1960
Creator: Gorton, H. C.; Mengali, O. J.; Zacaroli, A. R.; Crooks, R. K.; Swartz, J. M. & Peet, C. S.
Partner: UNT Libraries Government Documents Department
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FUEL BURNUP STUDIES FOR A 225 Mwe ADVANCED SODIUM GRAPHITE REACTOR

Description: Reactivity and fuel burnup studies were performed for a 255 Mw(e) sodium- graphite reactor of the advanced calandria core type. This reactor is briefly described. Initial criticality calculations and flux distributions were obtained, using two-group theory for enrichments between 2.0 at.% U/sup 325/ and 4.0 at.% U235. A four-group burnup study was performed for enrichments between 2.5 at.% Uisup nd 3.25 at.% U/sup 235/. Core lifetime, changes in isotopic fuel composition, variations in radial p… more
Date: June 15, 1960
Creator: Aronson, A. L.
Partner: UNT Libraries Government Documents Department
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Viewing Equipment for Use in the HRT Core and Blanket Vessels

Description: S>Several viewing devices were built or purchased and various viewing aids were developed to permit examination of the core vessel of the Homogeneous Reactor Test. The hole in the core vessel was viewed and photographed from both the inside and the outside. A number of simple periscopes were designed and fabricated. A small television camera was purchased, and manipulators were built to insent it in the core or in the blanket. A radiation-resistant 21-ft-long periscope was procured which is … more
Date: March 15, 1960
Creator: Culver, J. S.
Partner: UNT Libraries Government Documents Department
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STUDY OF FUEL TEMPERATURE AND FLOW EFFECTS OF PLUGGING IN SRE FUEL CHANNELS

Description: The fuel surface temperatures and flow rate effects which might be produced by plugs in SRE fuel channels were investigated. It was found that plugs which locally insulate more than 20 to 30% of the surface of a fuel rod are dangerous. Heat transfer through the mcderator would not significantly affect the sensitivity of the outlet thermocouple to change in mass flow through a fuel channel, provided the reactor power is above 2 Mw and the channel is not completely plugged. If a 5% or greater inc… more
Date: March 15, 1960
Creator: Noyes, R.C.
Partner: UNT Libraries Government Documents Department
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