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Operation of the Sodium Technology Loop for Contamination Meter Evaluations

Description: Report issued by the APDA over studies conducted on the Sodium Technology Loop. Methods, equipment, and results of the studies are presented and discussed. This report includes tables, illustrations, and photographs.
Date: March 25, 1964
Partner: UNT Libraries Government Documents Department
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Loading and operating conditions for charge of five NIE-1 fuel tubes and two target assemblies in KER-1 or KER-2 Production Test IP-584-D, Supplement B

Description: Production Test IP-584-D, Supplement B authorized the irradiation of target assemblies in KER-1 and KER-2. Furthermore, the production test authorized that these target assemblies be irradiated with)other approved production tests; for this test, N Reactor inner fuel elements (NIE-1) will be irradiated. The production test required that specific operating conditions and loading patterns would be approved by the managers of Testing, Process and Reactor Development, and Process Technology Subsect… more
Date: May 25, 1964
Creator: Deobald, T. L.
Partner: UNT Libraries Government Documents Department
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Modified tubular support patterns: Ribbed and ribless process tubes

Description: Reactor support charge designs and patterns have been numerous and varied over the past few years, the basis for acceptance of a particular support loading being determined from a consideration of fabrication costs and the hydraulic characteristics of the proposed dummy load as it applies to a particular reactor. Since the first three or four dummy pieces downstream of the fuel column (and upstream of the column in a spline tube) are discarded after the irradiation process, it is desirable to u… more
Date: August 25, 1964
Creator: Angle, C. W.
Partner: UNT Libraries Government Documents Department
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Production test IP-695-A thorium oxide irradiation: K Reactors

Description: Irradiation of thorium for the production of ``clean`` U-233 at HAPO began in CY 1963. Several small-scale tests, involving from gram size quantities up to a few elements, were successfully conducted and the results from these tests, coupled with theoretical predictions, indicated the desirability of further investigation. This test is one of the final steps in the pilot irradiations of ton quantities of thorium oxide target elements. The objectives of this test are to (1) authorize the irradia… more
Date: June 25, 1964
Creator: Hladek, K. L. & Gross, P. D.
Partner: UNT Libraries Government Documents Department
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Specification for enriched uranium billets for a coproduct demonstration in N-Reactor

Description: This document provides the specifications for the uranium billets to be used for fabrication of the driver fuel elements for a coproducer demonstration in N-Reactor. The specifications for uranium billets for the standard tube and tube geometry are listed in HW-67575 Rev3, ``Specifications for Uranium Metal Billets for NPR Fuel Elements,`` July, 1963, and in HW-76155 REV3, ``Chemical Specifications for Uranium Billets for NPR Fuel Elements,`` dated June 12, 1964. This document specifies the exc… more
Date: June 25, 1964
Creator: Nickolaus, J. W.
Partner: UNT Libraries Government Documents Department
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The use of chemical additives to improve first cycle decontamination at Purex

Description: The decontamination cycle (HA) at Purex has occasionally responded favorably to additions of waste rework material. The effect, exhibited in increased extraction of plutonium and improved decontamination from fission products has become known as the ``Tonic effect.`` Efforts to find the agent or agents in waste rework which are responsible for this effect have not been successful. Workers at ORNL, principally C. A. Blake, found that various materials decreased the distribution ratios of zirconi… more
Date: September 25, 1964
Creator: McKenzie, T. R.
Partner: UNT Libraries Government Documents Department
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N-Reactor Department Research and Development budget for FY 1966 and revision of budget for FY 1965

Description: The N-Reactor Department Research and Development Program for FY 1965, 1966, and later years is structured to achieve the following general goals. (1) Assurance of a high level of nuclear safety; (2) Assurance of achieving full plant life; (3) Reduction in operating costs for a given production rate; (4) Increase in production rate without proportionate increase in operating costs; (5) Savings in capital outlays necessary to achieve stated reductions in operating cost or increases in production… more
Date: March 25, 1964
Partner: UNT Libraries Government Documents Department
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Developmental requirements for canning a low density thoria demonstration load

Description: The feasibility of fabricating aluminum clad, low-density ({approximately} 65 per cent theoretical density) thoria elements using thoria produced-by a modified Sol Gel process, low frequency-low energy vibration for compaction, and the TIG welding process for closure welding has been demonstrated by Hanford Laboratories (HL). They have also assembled thoria fuel elements for the initial irradiation to produce 1 to 2 kgs. of U-233. At this time, it is expected that Hanford will be asked to produ… more
Date: February 25, 1964
Creator: Huff, G. A.; Knight, F. W.; Padgett, E. V. & Powers, H. G.
Partner: UNT Libraries Government Documents Department
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Calibration System for Cryogenic Temperature Transducers

Description: To provide the NERVA test program with a temperature measurement system of sufficient accuracy to satify present and future requirements, a cryogenic temperature measuring system was designed and developed employing a platinum resistance thermometer (RTT) as the sensor.
Date: September 25, 1964
Partner: UNT Libraries Government Documents Department
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The 25-Inch Liquid Hydrogen Bubble Chamber

Description: No Description Available.
Date: May 25, 1964
Creator: Barrera, F.; Byrns, R. A.; Eckman, G. J.; Hernandez, H. P.; Norgren, D. U.; Shand, A. J. et al.
Partner: UNT Libraries Government Documents Department
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OPERATION OF THE SODIUM TECHNOLOGY LOOP FOR CONTAMINATION METER EVALUATIONS

Description: The Blake Rhometer operating range was extended from 600 to 1000 deg F and a variable-orifice plugging meter was developed. Both instruments were evaluated in the Atomic Power Development Associates Scdium Technology Loop against weighed or metered contaminants. The loop injection series included: water, hydrogen, carbon monoxide, carbon dioxide, and methane gases; and tea bag injections of sodium carbonate, sodium hydride, sodium hydroxide, and sodium monoxide. Cover gas was monitored and temp… more
Date: March 25, 1964
Partner: UNT Libraries Government Documents Department
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Foam Suppression of Radioactive Iodine and Particulates

Description: " A reliable, efficient and economical method is needed to remove radioactive halogens such as iodine and bromine and particulates from air in many atomic energy installations. One method we have developed which is particularly suited to reactor containment vessels or other large confined areas is foam containment. In this method an ether lauryl sulfate foam containing an iodine reactant is generated, rapidly filling the entire containment volume. This provides a tremendous surface area to w… more
Date: February 25, 1964
Creator: Yoder, Robert E.; Fontana, Mario H. & Silverman, Leslie
Partner: UNT Libraries Government Documents Department
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The Isotope Shift of the Uranium Ka1 X Ray

Description: Technical report. From Introduction : "The nuclear volume dependent isotope shift of optical spectral lines has long been a very useful means for studying the changes in the nuclear size or shape for different isotopes of heavy elements."
Date: June 25, 1964
Creator: Brockmeier, R.; Boehm, F. & Hatch, E. N.
Partner: UNT Libraries Government Documents Department
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FATT--A TRANSIENT TEMPERATURE COMPUTER PROGRAM FOR THE EGCR CORE

Description: The computer program FATT for calculating the transient temperature distribution in the EGCR core is described. The program, in FORTRAN for the IBM 7090, provides an arbitrary choice of axial increments for the reactor core. The heat transfer coefficients are made temperature-dependent. Provisions are available for plotiing the results from the program on the Calcomp plotter. The equations and some typical results are included, and the finlte difference method of solution is described. (auth)
Date: February 25, 1964
Creator: Keeton, Don C.
Partner: UNT Libraries Government Documents Department
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