37 Matching Results

Search Results

Results: 1 - 24 next
open access

Reconnaissance for Uranium in the Tocopilla area, Province of Antofagasta, Chile

Description: Abstract: In September-October 1958 a six-day reconnaissance in the Tocopilla area, Antofagasta Province, Chile, was made by members of the U.S. Atomic Energy Commission and the Instituto de Investigaciones Geológicas de Chile for the purpose of evaluating reported uranium occurrences.
Date: February 1959
Creator: Bowes, William A.; Knowles, Paul H.; C., Mario Serrano & S., Rudolfo Grüenwald
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Yankee Atomic Electric Company Research and Development Program: Quarterly Progress Report: October 1, 1958 to December 31, 1958

Description: Quarterly report describing the technical research and development work accomplished by the Yankee Atomic Electric Company Research and Development Program, and documenting progress made on the group's various projects and goals.
Date: February 16, 1959
Creator: Garbe, R. W. & Walchli, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Report of the Fluid Fuel Reactors Task Force

Description: From preface: This report was prepared by a task force that met continuously in January and February of 1959 for the purposes of making a relative comparison of the fluid fuel reactor concepts for technical feasibility.
Date: February 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Automatic Control and Load Swing Tests. Test Results DL-S-144 (T-554924). Section I

Description: The purpose of this test was to determine the controlling ability of the Reactor Power and Temperature Control System and to determine the operational characteristics of the station during load swings. The Reactor Power and Temperature Control System satisfactorily controlled rod movements to maintain all primary plant parameters within their individual limits during steady state operation, ramp functions load changes and a peak xenon burnout transient. The operational characteristics of the st… more
Date: February 10, 1959
Creator: Baird, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Control Rod Positions for Criticality. Section I. Third Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure. The critical bank heights and bank worths were determined for various rod combinations are charted in the report.
Date: February 12, 1959
Creator: Baird, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of the Chemical Characteristics of the 1C Boiler. Test Results DL-S-209. Section III

Description: The purpose of the test was to determine the chemical operating characteristics of the 1C Boiler. The results of the tests performed on the 1C Boiler prior to the installation of new riser indicated that definite chemical hideout existed during full load operation of the boiler. Measurement of local concentrations further indicated that a stabilized steam picket existed in the upper region of the heat exchanger adjacent to the inlet tube sheet during high steaming rates. Since these test were p… more
Date: February 9, 1959
Creator: Kline, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Rod Drop Transient. Test Results DL-S-247 (T-641323). Section I

Description: The purpose of the test was to obtain data on plant performance after a single rod has been dropped with the plant at 13 mw gross generator output. The operation of the plant after a single control rod (No. 23) had been dropped was within allowable limits. The high speed recorder charts could not be evaluated accurately due to the fast chart speed and also because they were calibrated to cover a much wider range than was necessary. The necessary data was obtained from the normal plant records i… more
Date: February 16, 1959
Creator: Price, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Low-Energy [pi] Mesons in the Cosmic Radiation

Description: The intensity of 𝜋 mesons in the atmosphere is investigated in the energy region 𝐸kin≲50 Mev at sea level and at mountain altitudes. Positive 𝜋 mesons coming to rest in an absorber-scintillator are identified by the characteristic 𝜋−𝜇 decay. They are detected electronically and recorded photographically. The value 1.45±0.09 is adopted for the negative-to-positive ratio at small energies. The omnidirectional intensities 𝐽𝜋+ of slow positive 𝜋 mesons at sea level (91m), Echo Lake, Colorado (326… more
Date: February 2, 1959
Creator: Fotino, Mircea
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Processing of the Commission Blend of Colorado Front Range Uranium Ores

Description: Acid and alkaline processing of Commission Blend Colorado Front Range uranium ores is described. The composition of the blend is listed according to source and chemical composition. The processes investigated in laboratory and pilot plant work included concurrent and countercurrent acid leaching, alkaline leaching, and recycle of alkaline leach solution. In addition pre-roasting followed by acid and alkaline leaching, flotation of carbon and sulfides followed by acid leaching the concentrate, a… more
Date: February 1959
Creator: Nichols, I. L. (Ivan L.); Ross, J. R.; Tame, K. E. & Rosenbaum, J. B. (Joe B.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Rod Drop Transient Test. Test Results DL-S-247 (T-641323). Section II

Description: The purpose of the test was to obtain data on plant performance after a single control rod has been dropped with the plant at 40 mw gross generator output. The operation of the plant after a single control rod (No. 23) had been dropped with within the allowable limits. The information obtained from the high speed recorders could not be evaluated accurately due to the fast chart speed and also because they were calibrated to cover a much wider range than was necessary. The necessary data was obt… more
Date: February 12, 1959
Creator: Heas, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Processing of the Cotter Blend of Colorado Front Range Uranium Ores

Description: The results of laboratory and pilot plant alkaline leaching of the calcareous Cotter Blend are described. The Cotter Blend composition is given in relation to the source and chemical composition. It was demonstrated that specification-grade yellow cake with high recovery of uranium could be produced from Cotter Blend by a pressure alkaline leaching process. A pressure leach under oxygen pressure followed by caustic precipitation recovered 93.1% of the Uranium. (J.R.D.);
Date: February 1959
Creator: Nichols, I. L. (Ivan L.); Tame, K. E. & Rosenbaum, J. B. (Joe B.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Chemistry and Nuclear Chemistry of the Heavy Elements : Progress Report No. 4

Description: This progress report covers the work on the project approximately between the dates June 1, 1058 and May 30, 1959, and is being submitted ahead of the contractual expiration date to support the request for renewal action. During the previous year work has continued to progress in the nuclear and inorganic sections of our heavy element group. The low-level counting equipment will make it possible to extend our fission studies to much lower energies. The U235 and U236 alpha induced fission is ess… more
Date: February 1959
Creator: Cobble, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Scavenging of Particulate Matter in Connection with Nuclear-Powered Ships

Description: Gases, aerosols, and hydrosols are the forms of particulate matter which might be released from nuclear powered ships. Methods for scavenging these materials were studied in detail. Visual and radar techniques were used in tracking gases and aerosols in the free atmosphere. Scavenging of radioactivity dispersed in substitute ocean water by a permanganate-ferrous salt system was studied. A schematic diagram of a pneumatic conveying system for this type of scavenging material is provided.
Date: February 6, 1959
Creator: Rosinski, John
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Technical Progress Report

Description: Progress is reported on high-speed computer program, mathematical methods, switching circuit theory, ILLIAC use and operation, IBM 650 use and operation; and general laboratory information.
Date: February 1959
Creator: Digital Computer Laboratory, University of Illinois Graduate College
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uranium Reconnaissance and Drilling in the Sanostee Area, San Juan County, New Mexico and Apache County, Arizona

Description: Report documenting work to map in detail the Roy Mesa and Enos Johnson claim areas so that ore guides could be determined and the areas could be evaluated for drilling and to complete a general reconnasaince of the favorable Mesozoic.
Date: February 1959
Creator: Blagbrough, John W.; Thieme, D. A.; Archer, B. J., Jr. & Lott, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Synopsis of Studies Related to Tritium Monitoring and Personnel Protective Techniques

Description: Technical report issued by E. I. du Pont de Nemours & Co. From Abstract: "Information obtained from investigations pertinent to tritium monitoring and protective measures at the Savannah River Plant are given. These findings were used to establish realistic protective techniques and consequently, to insure the safety of workers exposed to this hazard. Topics included are: contamination, permeation of plastics and rubber, instrumentation, and biological and physical aspects."
Date: February 1959
Creator: Butler, Harry L. & Van Wyck, Robert W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Manganese Dioxide Precipitation in Uranium - Aluminum Nitrate Solutions

Description: Technical report. From Abstract: "Precipitation of manganese dioxide in solutions of uranium-aluminum alloy effected maximum removal of fission products when the alloy solutions were acid deficient. Minimum adsorption of uranium and minimum volume of centrifuged MnO2 were obtained by precipitation in acidic solutions with vigorous agitation."
Date: February 1959
Creator: Henry, Hugh E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen