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The Salt Cycle Process

Description: The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the red… more
Date: August 1, 1960
Creator: Benedict, G.E.; Lyon, W.L.; Mudge, L.K.; Swanson, J.L. & Walling, M.T. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modified Purification System Performance Test. Core I, Seed 2. Test Results (T-641124). Section 1

Description: An investigation was conducted to establish an operating procedure for flushing water through a purification system demineralizer which was out of service for an extended period, and to determine the demineralizer serviceability. (J.R.D.)
Date: September 14, 1960
Creator: Duquesne Light Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Hazards Encountered in Arc Melting Thorium

Description: A project to provide information on the hazards associated wlth arc melting of Th is described. A general airsampling analysis was made to determine the separation, concentration, and distribution of Th daughter (decay) products throughout arc melting, machining, and forging processes found in a handling facility. The value of well coordinated health physics program is stressed in connection with potential health hazards and personnel protection. Building, equipment, and exhaust ventilation req… more
Date: November 1, 1960
Creator: Lowery, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TEST OF GERMAN UNDERGROUND PERSONNEL SHELTERS

Description: The predicted behavior of German underground personnel shelters, equipment, and certain instrumentation was investigated. Data obtained will be used for evaluation and improvement of present design criteria. Nine reinforcedconcrete underground shelters, designed by German engineers, were tested at the 170-, 155-, 110-, 78-, 26-, 11.5-, and 7.2-psi overpressure ranges as determined from average blast-line instrumentation measurements. Reinforcing steel, doors, and ventilation equipment were rece… more
Date: July 1, 1960
Creator: Cohen, E. & Bottenhofer, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 7 for April 1, 1960 to June 30, 1960

Description: High-temperature x-ray diffraction experiments provided confirming evidence regarding the origin of the metastable gamma phase and of the general features of the zirconiumhydrogen phase system. These experiments also showed that the reaction alpha + delta -- beta (the eutectoid reactlon on heating) proceeds at an extraordinarily slow rate, although the reverse reaction proceeds so rapidly that beta phase cannot be retained to room temperature by quenching. The sluggishness of the eutectoid reac… more
Date: July 1, 1960
Creator: Beck, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Laboratory Investigation of Decontaminating Solutions for Primary Loop Decontamination in the New Production Reactor

Description: An investigation was made of methods for decontaminating the primary loop of the New Production Reactor (NPR). Decontamination factors ranging from fifty to several thousand were obtained with several different combinations of cleaning solutions. In general, fission product activity was removed to a lower residual level than was activated corrosion product activity, and carbon steel was easier to decontaminate than was stainless steel. It was necessary to completely remove the oxide film from t… more
Date: November 1, 1960
Creator: Mendel, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING, SEPTEMBER 30, 1960

Description: The feasibility was studied and a cost estimate prepared of an experimental reactor to determine the operating characteristics of beryllia- moderated, gas-cooled systems wtthin a power limit of 10 Mw(t). The heat energy produced by the experimental reactor is to be dissipated in a heat dump. No machinery for production of power was to be provided. Other requirements were that the reactor should be capable of testing core types different from the current MGCR design, and the system should permit… more
Date: September 30, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Buried Conduits as Personnel Shelters

Description: Supersedes ITR-1421. Twelve large-diameter buried conduit sections of various shapes were tested in the 60- to l49-psi overpressure region of Burst Priscilla to make an empirical determination of the degree of personnel protection afforded by commercially available steel and concrete conduits at depths of burial of 5, 7.5, and 10 feet below grade. Essentially, it was desired to assure that Repartment of Defense Class I, 100psi and comparable radiations, and Class II, 50-psi and comparable radia… more
Date: July 14, 1960
Creator: Albright, G. H.; LeDoux, J. C. & Mitchell, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. GCRE-I HAZARDS SUMMARY REPORT. ADDENDUM III

Description: The hazards evaluation was modified to reflect certain changes made to the equipment as a result of operating experience. These changes included: the addition of a startup interlock circuit; the modification of a startup interlock circuit; several minor modifications to the control rod actuators; and the addition of the tube-sheet cooling system. (M.C.G.)
Date: May 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY

Description: For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date: January 1, 1960
Creator: Gronemeyer, F.C. & Merryman, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermoelectric Materials. Final Report, January 28, 1959-July 28, 1960

Description: BS> A method for the measurement of thermal conductivities of electrically conducting materials at temperatures in excess of 1000 deg C with a high accuracy was devised. The spatial boron concentration gradient in boron- doped graphite to achieve maximum p-type thermoelectric output was established. The production of an n-type silicon carbide-graphite composit was studied. Theoretical studies produced a detailed picture of the effect of doping on the electronic properties of graphite. A method … more
Date: August 15, 1960
Creator: Brechenridge, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of the Maximum Credible Accident Relevant to the Design of the Containment Shell, Experimental Low-Temperature Process Heat Reactor Project

Description: The effects of the maximum credible accident relative to the design of the containment shell are discussed. The maximum credible accident is defined. The thermal and hydraulic effects of the maximum credible accident on the reactor system were analyzed. The extent to which fuelrod cladding will melt was estimated. The amount of energy released from the reactor system by the escaping steam and water and by a possible chemical reaction was calculated along with the corresponding pressure rise ins… more
Date: March 21, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Liquid-Phase Sintering Techniques for Molybdenum Alloys. Final Report

Description: An envelope-type microstructure produced by liquidphase sintering techniques was used to develop ductiIe molybdenum-base alloys for sodium-cooled fast reactor application. A total of 105 compositions was examined; 21 showed evidence of room-temperature ductility, and a number of other compositions appeared promising. The prerequisites for obtaining ductile liquid-phase sintered materials were demonstrated. The most ductile alloys produced are based on the Mo--Pd--Cu and Mo --W--Ni--Fe systems. … more
Date: November 10, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey of Reactor Plant Container and Components After Shutdown "F" Survey. Core I, Seed 1. Test Results (T-612076). Section 4

Description: An investigation was conducted to obtain measurements of radiation levels inside the hemispherical heads of the 1-B heat exchanger. The radiation levels were measured at the handholes on two occasions with an interval of 640 hrs between them. A very large increase was noted and could be explained only by the possibility that the measurement survey points were not identical. (J.R.D.)
Date: October 17, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

[Leon Breeden Scrapbook: 1960]

Description: Scrapbook of materials including photographs, letters, newspaper clippings, performance programs, and various other notes and ephemera documenting the activities of the North Texas State College One O'Clock Lab Band during 1960.
Date: 1960~
Creator: Breeden, Leon
Item Type: Refine your search to only Book
Partner: UNT Music Library
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