476 Matching Results

Search Results

Results: 1 - 24 next
open access

1A Reactor Inlet Hydraulic Valve Position Detector Temperature. Section I. Core I, Seed 1. Test Results DL-S-258-S, RNI-3

Description: The purpose of the test was to determine the internal temperature of the valve position detector for the 1A reactor inlet hydraulic valve with the plant at normal pressure and temperature and at power. The normal operating temperatures for the valve position detector on the 1A reactor inlet hydraulic valve range from a minimum of 287 F to a maximum of 294.7 F.
Date: November 20, 1959
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department monthly report for October 1959

Description: Pu output from separations plant was less than scheduled, but year-to- date production exceeded commitment by 4%. The Palm recovery run in Purex was the most successful to date. UO{sub 3} production and shipments met schedule. Purex had two pump failures. When Purex 1WW was centrifuged and treated to recover Ce, most of it remained in the centrifugate; only 14% was recovered. The prototype Pu ozonator in Redox performed well. Test runs on an acid precycle flowsheet and a proposed internal recyc… more
Date: November 20, 1959
Partner: UNT Libraries Government Documents Department
open access

Diffusion of Xenon in Columbium

Description: The diffusion coefficient was calculated for the diffusion of Xe through Nb and found to be 0.064 exp (-18,600/RT).
Date: November 20, 1959
Creator: Gregory, D. P. (Derek P.) & Leavenworth, H. W. (Howard W.)
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department Monthly Record Report: October 1959

Description: This document details activities of the irradiation processing department during the month of October, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor operations; Facilities Engineering operation; Employee Relations Operation; and Financial operation.
Date: November 20, 1959
Partner: UNT Libraries Government Documents Department
open access

PHASE DIAGRAMS OF NUCLEAR REACTOR MATERIALS

Description: This compilation presents the phase diagrams for possible materials for nuclear reactors developed at the Oak Ridge National Laboratory over the period 1950 to 1959. The systems covered are: metal, metal-fused-salt, fusedsalt, oxide, hydroxide, and aquecus. (W. L. H.)
Date: November 20, 1959
Creator: Thoma, R.E. ed.
Partner: UNT Libraries Government Documents Department
open access

Single tube flow rates at low header pressures with nozzle caps removed: All reactors

Description: Laboratory data of flow rate versus header pressure were obtained for various conditions of nozzle cap removal from C, K and BDF single tube mockups of central zone tube assemblies using I&E slug charges. The data are presented. Suggestions are made for applying the data to DR and H reactors. In general, the effect of a pre-inserted support charge on the flow rate is small, especially with the front nozzle cap on. It should be noted that pre-insertion of an entire (117 inch long) support charge… more
Date: November 20, 1959
Creator: Waters, E. D.
Partner: UNT Libraries Government Documents Department
open access

Characterization of Surfactants in Aluminum-Uranium Fuel Reprocessing Solutions

Description: Surface active materials in aluminum nitrate-nitric acid fuel reprocessing solutions were characterized. Polymerized silica, zirconium- modified silica and soluble dibutyl phosphate species were found to contribute to stable emulsion formation. These surfactants were reduced in effectiveness by added acid. (auth)
Date: October 20, 1959
Creator: Cannon, R. D.
Partner: UNT Libraries Government Documents Department
open access

THE PREPARATION OF URANIUM DIOXIDE FROM A MOLTEN SALT SOLUTION OF URANYL CHLORIDE

Description: Uranium oxides in a molten eutectic mixture of NaClKCl were chlorinated by bubbling chlorine gas through the mixture. The reaction product, uranyl chloride. was soluble in the molten salt. Although UO/sub 2/ was the most common oxide used, the reaction was similar in the other oxides. Phosgene and aluminum chloride were also used as chlorinating agents. A dense, crystalline precipitate of pure UO/sub 2/ was prepared by the reduction of the uranyl chloride contained in the molten salt solution. … more
Date: October 20, 1959
Creator: Lyon, W.L. & Voiland, E.E.
Partner: UNT Libraries Government Documents Department
open access

THE SOLID SOLUBILITY AND CONSTITUTION OF YTTRIUM IN IRON-20 TO 40 w/o CHROMIUM ALLOYS

Description: The solid solubility of yttrium in iron-20 to 40 wt.% chromium alloys was determined by metallographic techniques and found to be extremely small. At 1320 deg C, the maximum solubility is about 0.12 wt. a yttrium. Study of iron- rich alloys of the iron-yttrium system shows that the compound YFe/sub 5/ exists. A eutectic occurs between iron and YFe/sub 5/ at 1257 deg C. The constitution of iron - 20 to 40 wt.% chromium-yttrium alloys ccntaining less than 6 wt.% yttrium was studied between 1250 a… more
Date: October 20, 1959
Creator: Farkas, Martin S. & Bauer, Arthur A.
Partner: UNT Libraries Government Documents Department
open access

709 Program for Reduction of Exponential Pile Data

Description: A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
Date: August 20, 1959
Creator: Matsumoto, D. D.
Partner: UNT Libraries Government Documents Department
open access

Incontamination of Pig Skin Contaminated With a Plutonium Solution

Description: Different methods of decontaminating plutonium contaminated skin were studied by contamination localized areas of pig skin and then testing the different decontamination methods. Results indicate that the most effective of the decontamination methods tested involved the application of a plastic adherent material to the skin and its later removal by peeling.
Date: August 20, 1959
Creator: George, L. A.; Dockum, H. L. & Bustad, L. K.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout. Letter Report No. 8 Covering Period June 1 to August 1, 1959

Description: Progress is reported on the separation of airborne particles into size fractions for radioactive analysis. Laboratory studies of scavenging systems were conducted using a latex suspension diluted 1 to 500 parts with polystyrene then atomized with a Lauterbach generator. Tests were conducted for the collection of polystyrene particles by an evaporating water droplet. The results from these tests are included. The size distributions of particles obtained from atomizing latex and 1% gelatin suspen… more
Date: August 20, 1959
Creator: Stockham, J. & Rosinski, J.
Partner: UNT Libraries Government Documents Department
open access

Techniques for Estimating the Specific Retention Properties of Hanford Soils

Description: Disposal on a specific retention basic of certain radioactive liquid waste solutions emanating from separations from separations plants has been practiced at Hanford since 1944. As used at Hanford, the term "specific retention" is defined as that volume of waste liquids that may be disposed to the soil* and be held against the force of gravity by the molecular attraction between sand grains and the surface tension of the water, when expressed as percent of packed soil volume. In practice it rep… more
Date: August 20, 1959
Creator: Bierschenk, William H.
Partner: UNT Libraries Government Documents Department
open access

Centrifugal Casting of Aluminum-Uranium Alloys

Description: "Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 w/o uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced stilizing a pouring temperature of 2400 F, a heavy-walled steel cylinder rotating between 700 to 900 rpm for the mold and bottom-pouring technique employi… more
Date: July 20, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department
open access

CENTRIFUGAL CASTING OF ALUMINUM-URANIUM ALLOYS

Description: Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 wt.% uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced utilizing a pouring temperature of 2400 ction prod- , a heavy-walled steel cylinder rotating between 700 and 900 rpm for the mold and a bottom-pouring tec… more
Date: July 20, 1959
Creator: Daniel, N.E.; Foster, E.L. Jr. & Dickerson, R.F.
Partner: UNT Libraries Government Documents Department
open access

Investigation Of Windows And Shields For Neutron Point Sources

Description: An empirical approach for the evaluation of shielding materials for macrochemical manipulations of spontaneously fissioning heavy elements (curium and californium) has revealed interesting comparisons. High-density metal halide solutions were compared with lead glass and with rare earth glass for use as shielding windows. Laminated shields of lead-paraffin and uranium-paraffin were compared with water and with paraffin for shielding walls.
Date: May 20, 1959
Creator: Browne, Howard J.; Kaufmann, John A. & Garden, Nelson B.
Partner: UNT Libraries Government Documents Department
open access

Nuclear and Radiation Hazards Evaluation of SRE Fuel Processing and Storage

Description: Nuclear and radiation hazards have been investigated for all phases of operation to be carried out in the mechanical decladding of SRE fuel elements. The SRE fuel is 2.8% enriched with a maximum burnup of 1,000 Mvd/ton and minimum cooling of 120 days. Each element contains 9 kg of uranium metal (~2 kg U-235) and is made up from 84 slugs (3/4"D x 6'"), clad with (10 mil wall) stainless steel tubing. It is planned to ship the fuel from Santa Susana, California, to Oak Ridge in the modified PAR l… more
Date: May 20, 1959
Creator: Suddath, J. C.
Partner: UNT Libraries Government Documents Department
open access

Parameters of Dissolver Equipment Design - Power Fuel Reprocessing

Description: The Interim Power Fuels Reprocessing Program, as established by the Atomic Energy Commission, provides the service of recovering uranium, thorium, plutonium, etc., from irradiated fuels discharged from non-production reactors of both public and private ownership. To provide this service on an interim basis and at minimum capital investment, the Commission has assigned the processing responsibility for the various fuel types to several AEC sites. The sites are to be assigned fuel types most simi… more
Date: May 20, 1959
Creator: Graf, W. A.
Partner: UNT Libraries Government Documents Department
open access

The Rhode Island and Providence Plantations Atomic Energy Commission Nuclear Science Center Volume II - Safeguard Report

Description: This report presents the description and safeguard evaluation of an open pool research and test reactor rated at one megawatt. The reactor is being proposed by the General Electric Company to the Rhode Island and Providence Plantation Atomic Energy Commission.
Date: May 20, 1959
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
open access

Survey: Oxidation Characteristics of Columbium and Columbium Base Alloys

Description: Unclassified experimental data concerned with the oxidation characteristics of Nb and Nb-base alloys are presented. The bulk of the results is presented in tabular form and cataloged under laboratory name sub-headings. The theory of alloy development for oxidation resistance is discussed. Methods of evaluating oxidation behavior are outlined.
Date: May 20, 1959
Creator: Clough, W. R. (William Raymond); Hirakis, E. C. & Krutenat, R. C.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen