11 Matching Results

Search Results

Results: 1 - 11
open access

Radiation Damage to Organic Ion-Exchange Materials

Description: From abstract: "The stability of polystyrene and phenolic ion-exchange resins to radiation from a Co60 source and from absorbed Ce144-PR144 was investigated. Sulfonated polystyrene cation-exchange resins lost 10 to 20% of their capacity per watt-hour of radiation absorbed per gram of oven-dry resin, while the quaternary amine anion-exchange polystyrene resins lost about 40%. Phenolic cation-exchange resins lost only 1%."
Date: March 16, 1953
Creator: Higgins, I. R.
Partner: UNT Libraries Government Documents Department
open access

Statistical Evaluation of Methods for the Analysis of Dibasic Aluminum Nitrate (DIBAN)

Description: The indicated methods for determining the following constituents of Diban, which is an aqueous solution of dibasic aluminum nitrate, Al(OH)2NO3, were evaluated statistically: 1aluminum by gravimetric, volumetric, and spectrophotometric procedures, 2. basicity (hydroxyl value) by formation of an aluminum complex and titration of the free acid with standard alkali solution, 3. total nitrogen by the Kjeldahl method, 4. ammonia by the Kjeldahl method, and 5. nitrates by means of a cation-exchange r… more
Date: September 16, 1955
Creator: Surak, J. G.; Thomason, P. F. & Haaen, H. P.
Partner: UNT Libraries Government Documents Department
open access

Solid State Division Semiannual Progress Report for Period Ending August 31, 1955

Description: LITR Fluoride-Fuel Loop. — The inconel loop was dismantled for removal of the samples and for recovery of the uranium by using the remote cutting tools installed in a half cell of the Solid State Building. Disassembly proceeded without incident. An electric-arc cutting technique was developed for removal of the stainless steel enclosure around the pump bowl. Fission power and maximum flux were determined by irradiating a simulated loop, by heat-balance calculations, by radiochemical analyses fo… more
Date: November 16, 1955
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
open access

Products Produced in Continuous Neuron Irradiation of Thorium

Description: Calculated data and graphs describing the effects of continuous thermal-neutron irradiation of thorium, the usual method of operations of homogeneous reactors, are presented.The buildup and decay of U^233, Pa^233, other heavy isotopes, and fission products are considered on the basis of best available cross-section and fission-yield data. The effects of the heavy isotopes and fission products on neutron economy are discussed.
Date: February 16, 1956
Creator: Gresky, A. T. & Arnold, E. D.
Partner: UNT Libraries Government Documents Department
open access

Metallurgy Division Annual Progress Report, September 1, 1959

Description: Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date: December 16, 1959
Creator: Oak Ridge National Laboratory. Metallurgy Division.
Partner: UNT Libraries Government Documents Department
open access

Health Physics Instrument Manual

Description: Report issued by the Oak Ridge National Laboratory discussing a Health Physics Instrument Manual. Descriptions, characteristics, and applications of different instruments are presented. This report includes tables, illustrations, and photographs.
Date: May 16, 1963
Creator: Davis, D. M. & Gupton, E. D.
Partner: UNT Libraries Government Documents Department
open access

Analysis of Thorex Pilot Plant Radiation Exposures During 1955

Description: The Thorex Pilot Plant at Oak Ridge National Laboratory was operated during 1955, processing reactor-irradiated thorium slugs to recover U233 and thorium and 12 MTR fuel elements to recover U235 and Np237. The radiation exposure received by operating personnel during this period averaged 60 mrcp/man-week. Most radiation exposure was received in areas that were intended to be only slightly or nonradioactive. However, because insufficient decontamination of process solutions was achieved and equi… more
Date: November 16, 1956
Creator: McCarley W. T.
Partner: UNT Libraries Government Documents Department
open access

Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents

Description: The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date: December 16, 1960
Creator: Pierce, R. M.
Partner: UNT Libraries Government Documents Department
open access

Revised Version of HFIR Critical Experiment-2 (HFCE-2)

Description: A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date: January 16, 1961
Creator: Kasten, P. R. & Cheverton, R. D.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen