UNT Libraries Government Documents Department - 46 Matching Results

Search Results

Results: 1 - 24 next
open access

Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station

Description: This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.
Date: February 6, 1959
Creator: Commonwealth Edison Company
open access

Brookhaven National Laboratory Annual Report: 1958

Description: Report issued by the Brookhaven National Laboratory discussing the work conducted by the lab during the fiscal year of 1958. As stated in the introduction, "the progress and trends of the research program are presented along with a description of the operational, service, and administrative activities of the Laboratory" (p. vii). This report includes tables, illustrations, and photographs.
Date: February 1959
Creator: Brookhaven National Laboratory
open access

Chemical Reactivity of Uranium Monocarbide and Uranium Mononitride with Water at 100°C.

Description: The monocarbide and the mononitride of uranium are potentially useful ceramic nuclear fuel materials. This paper reports the results of exploratory investigations of the reactions of uranium monocarbide and uranium mononitride with boiling water. Uranium dioxide, chemically stable in deoxygenated boiling water, was used as a control.
Date: February 26, 1959
Creator: Newkirk, H. W.
open access

Concentration and Final Purification of Neptunium by Anion Exchange

Description: It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless s… more
Date: February 10, 1959
Creator: Ryan, J.L.
open access

Concentration of Plutonium by Cation Exchange -- Stabilization of Pu(Ill) in Nitric Acid

Description: Technical report. From Abstract : "Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid, reduced Pu(IV) rapidly and completely to Pu(III) in solutions of nitric acid. The solutions of Pu(III) were stable. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV)."
Date: February 1959
Creator: Tober, Frank W., 1919-1995 & Russell, Edwin R.
open access

Decontamination Program Task II. Volume 1, Contamination and Decontamination in Nuclear Power Reactors

Description: Abstract: A survey of the problem of reactor system contamination by radioactive material and methods that have been employed to remove the material was carried out. Following this survey, an investigation of chemical solutions was undertaken to find one which might be successfully employed in the decontamination of a stainless steel steam generator. From a preliminary screening, the most promising chemical method from the view point of minimum corrosion and maximum decontamination is a caus… more
Date: February 13, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
open access

Decontamination Program Task II. Volume II, Evaluation of Chemical Agents for Nuclear Reactor Decontamination

Description: Abstract: The caustic permanganate-rinse decontamination treatment was investigated. Loop and metallurgical studies were performed to determine optimum operating conditions as well as the metallurgical effects of the treatment. A treatment with 10 percent sodium hydroxide and 5 percent potassium permanganate solution followed by a rinse with a 5 percent ammonium citrate, 2 percent citric acid and 1/2 percent Versene solution was chosen for the decontamination of a stainless steel steam generat… more
Date: February 15, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
open access

Decontamination Program Task II. Volume III, Recommended Procedure for Decontamination of a Stainless Steel Steam Generator

Description: Abstract: A decontamination procedure for a stainless steel steam generator similar to the APPR-1 using a fill-flush application of a caustic permanganate-citrate combination solution is recommended. The isolation of the steam generator is to be accomplished by means of specially designed plugs at the reactor vessel outlet and at the primary coolant pumps. Anticipated results, including corrosion rates and decontamination factors, are presented.
Date: February 13, 1959
Creator: Pancer, Guyon P. & Zegger, John L.
open access

Detailed Procedure for K Reactors Rear ace Decontamination by Chemical Flush or the Rear Crossheaders, Pigtails and Nozzles as Authorized by the Production Test Authorization IP-239-N.

Description: The purpose of this procedure is to present a detailed, chronological presentation of the preliminary decontamination and post decontamination steps necessary to fulfill the requirements of the Production Test Authorization IP-239-N. The procedure attempts to present the required operation in sufficient detail to successfully accomplish the intent of the test. Certain procedures involve operations of a standard nature and have not been elaborated upon to any great extent, as it is expected tha… more
Date: February 25, 1959
Creator: Crossman, W.A.
open access

The Effect of Fabrication Variables on the Structure and Properties of UO₂-Stainless Steel Dispersion Fuel Plates

Description: From introduction: "This report deals with a part of the research and development studies which preceded the manufacture of fuel elements for the Gas Cooled Reactor Experiment (GCRE)." The studies evaluate the effects of varying the type and size of UO2 particles, stainless steel matrix powders, blending procedures, compacting pressures, sintering times, temperatures and atmospheres, roll-cladding temperatures and reduction rates, total cold reduction, and heat-treating times and temperatures h… more
Date: February 18, 1959
Creator: Paprocki, Stan J.; Keller, Donald L. & Cunningham, G. W.
open access

Flow Decay After an Electrical Power Outage in the PRTR

Description: Previously, W. S. Figg and T. W. Ambrose (HW-51767 Rev) have investigated the problem of flow decay following electrical power loss to the PRTR primary coolant pumps. However, since the time of their study many reactor piping changes have been made in the design; therefore, it has become advisable to re-examine the problem incorporating these changes.
Date: February 6, 1959
Creator: Muraoka, J.
open access

Fluidized Bed Reactor Study: Phase I - Feasibility

Description: From abstract: The Fluidized Bed Reactor (FBR) consists of a bed of fuel pellets which circulate in a confined core region as the result of the upward flow of fluid through the particles. In the present concept the fluid acts as a fluidizing, coolant and reactor moderator medium. This report is the results of the Phase I study to determine the feasibility of this concept.
Date: February 1959
open access

Geological Survey Investigations in the U12e.05 Tunnel, Nevada Test Site

Description: From introduction: The papers comprising the various parts of this report contain the preliminary results of the U. S. Geological Survey investigations in the Ul2e.05 tunnel at the Atomic Energy Commission's Nevada Test Site, Nye County, Nevada (fig. 1). Reports on electrical resistivity, natural radioactivity, and heat required to raise the rocks to 100C will be issued later. A preliminary report on the geologic effects of the Blanca event is being prepared.
Date: February 1959
Creator: Diment, William H.; Wilmarth, V. R.; Houser, F. N.; Dickey, D. D.; Hinrichs, E. Neal; Botinelly, Theodore et al.
open access

Heat Transfer in an Annulus with Asymmetric Heating

Description: Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. V. & Reynolds, William C., 1933-2004
open access

Heat Transfer in Radiant- Heat Spray Calcination

Description: The fixation of aqueous radioactive wastes in a stable solid media by means of calcination has been the subject of considerable research and development effort. Several methods of doing this on a continuous basis have been devised and a few have been demonstrated to be feasible for the handling of non-radioactive or low activity simulated wastes. Currently an investigation of calcination by means of radiant-heat spray drying is being carried on by the Chemical Research Operation of the Hanford … more
Date: February 1, 1959
Creator: Johnson, B.M., Jr.
open access

Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
open access

Ion Cyclotron Waves in Mirror Geometry

Description: The following report discusses technical problems with ion cyclotron waves, and to suggest a possible application to ion magnetron work.
Date: February 11, 1959
Creator: Furth, Harold P.
open access

Isopach Mapping by Photogeologic Methods as an Aid in the Location of Swales and Channels in the Monument Valley Area, Arizona

Description: Report discussing the mapping of the Monument Valley area in Arizona in order to locate uranium-vanadium deposits, which were localized in strata of the Shinarump member of the Chinle formation of Triassic age that fill ancient scour channels.
Date: February 1959
Creator: Witkind, Irving J.; Hemphill, William R.; Pillmore, Charles L. & Morris, Robert H.
Back to Top of Screen