43 Matching Results

Search Results

Results: 1 - 24 next
open access

Description of a capsule for irradiation of fuel specimens at high temperatures

Description: A controlled-temperature irradiation capsule was operated containing small fueled specimens at 160O to 1650 F. The design involved calculating the specimen heat-generation rate and designing an insulating gas gap around the specimens to achieve the desired temperature. Electric heaters were inserted to help control temperature. The thickness and composition of the gas gap were modified prior to operation on the basis of information on probable neutron flux obtained from a nuclear mock-ups and o… more
Date: April 22, 1959
Creator: Basham, S. J.; Stang, J. H.; Goldthwaite, W. H. & Dunnington, B. W.
Partner: UNT Libraries Government Documents Department
open access

Hexone Extraction-Coulometric Titration of Uranium

Description: Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.
Date: June 22, 1959
Creator: Blevins, E. L.
Partner: UNT Libraries Government Documents Department
open access

Hexone Extraction-Coulometric Titration of Uranium

Description: Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulfate media. Relative standard deviations of 0.43% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies. (auth)
Date: June 22, 1959
Creator: Blevins, E. L.
Partner: UNT Libraries Government Documents Department
open access

Survey of the Radiation Levels in the Containment Vessel of the Enrico Fermi Atomic Power Plant. Part 5. Gamma Radiation Levels on the Operating Floor of the Containment Building. A. Levels Above the Equipment Compartment. Technical Memorandum No. 16

Description: The results are presented of a survey of calculated gamma-ray levels at many points on the surface of the operating floor of the containment building for the Enrico Fermi reactor. That portion of the floor surveyed lies directly above the equipment compartment. The calculations were made with the aid of an IBM-650 electronic computer. The main source of radioactivity which gives rise to gamma radiation above the floor is the radioactive sodium-24 in the primary coolant system. This system was c… more
Date: December 22, 1959
Creator: Chaltron, W.F. & Hungerford, H.E.
Partner: UNT Libraries Government Documents Department
open access

High Current Electron Accelerator

Description: The following report describes the investigations of the microwave solution and the Astron solution, to produce high current electron beams.
Date: January 22, 1959
Creator: Christofilos, Nicholas C.
Partner: UNT Libraries Government Documents Department
open access

Flat Dispersion Plates Progress Report

Description: The enclosed report covers the work done under the subject contract at the Powder Metallurgy Laboratory, Stevens Institute of Technology, during the period September 1, 1959 through September 30, 1959.
Date: October 22, 1959
Creator: Comestock, Gregory J.
Partner: UNT Libraries Government Documents Department
open access

Core Parameter Study for a 300-Mw Sodium Graphite Reactor

Description: A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, a scale-up of the Hallam Power Reactor. The results of the study indicate that the core design is nsar optimum and that core modifications would reduce the power costs by less than 5%. The lattice spacing, fuel rod diameter, and sodium flow can be varied within a rather broad range without significant changes in power generation costs. The effect of the fuel cladning thickness is more significant… more
Date: October 22, 1959
Creator: Corcoran, W.P.
Partner: UNT Libraries Government Documents Department
open access

Limitations for Existing Storage Tanks for Radioactive Wastes from Separations Plants

Description: Continued process improvements in the separation plants provide an incentive for economics in waste storage costs by utilizing existing facilities to their maximum capability consistent with the radiological hazards involved. The major improvements have reduced waste volumes resulting in increased fission product concentration and energy potential. Analyses have been made to determine the effect of this change on the integrity of the existing structures.
Date: October 22, 1959
Creator: Doud, E.
Partner: UNT Libraries Government Documents Department
open access

Limitations for Existing Storage Tanks for Radioactive Wastes From Separations Plants

Description: The physical limitations of existing storage tanks for radioactive wastes from separations plants are defined as a guide for preparing process and operating criteria for the existing tank forms to assure continued integrity of the tanks. A "safe-load" curve for each of the four groups of tanks based on current technology is presented. Loading conditions, operation procedures, and thermal stresses are discussed. (M.C.G.)
Date: October 22, 1959
Creator: Doud, E. & Stivers, H.W.
Partner: UNT Libraries Government Documents Department
open access

Revised recommendations for the 100-K Area Project CG-775 raw water requirements

Description: As a part of Project CG-775, 100-K Area Water Plant Expansion, the capacity of the 181-K river pump installations will be increased. Recommendations for the raw water requirements based on a reactor flow of 175,000 gpm were presented in document HW-55877. Since then a new fuel element has been developed for the K reactors, resulting in a lower reactor system curve. It is recommended that the design criteria for the 181-K river pumps be based on a total raw water flow of 213,000 gpm with spare p… more
Date: June 22, 1959
Creator: Fifer, N. F.
Partner: UNT Libraries Government Documents Department
open access

Thermodynamic Properties of Carbides at High Temperatures

Description: Thermodynamic properties of the carbide or carbon saturated phases of Ti, Zr, U and Cr are not known accurately. Available data have been summarized by Brewer et al., and some recent measurements have been reported by Chupka and his associates. The purpose of this investigation is to obtain reliable data on the vapor pressures of metals in equilibrium with their carbides by means of graphite Knudsen cells. From the resulting data, the related thermodynamics properties can be calculated.
Date: September 22, 1959
Creator: Fujishiro, S. & Gokcen, N. A.
Partner: UNT Libraries Government Documents Department
open access

Modified Zirflex Process for Dissolution of Zirconium-and Niobium-Bearing Nuclear Fuels in Aqueous Fluoride Solutions: Laboratory Development

Description: Modified Zirflex process flowsheets were developed for recovering uranium from the newer power reactor fuel alloys after discharge from the reactor. The STR (1% U97% Zr-2% Sn) and EBWR Core-1 (93.5% U-5% Zr-1.5% Nb clad in Zircaloy-2) fuels are used as examples of low- and high-uranium fuels, respectively. A dissolvent of 6 M NH/sub 4/F yields a solution of zirconium and a precipitate of ammonium uranous fluoride. In one process, ammonium hydroxide is added to produce insoluble hydrous oxides o… more
Date: December 22, 1959
Creator: Gens, T. A. & Baird, F. G.
Partner: UNT Libraries Government Documents Department
open access

The Concentration of Peroxide in Uranyl Sulfate Solutions at Incipient Precipitation

Description: The concentrations of peroxide in uranyl sulfate solutions at incipient precipitation of uranium peroxide were determined over a temperature interval from 79 to 114'C. The results of the experimental observations have been used to calculate a self-consistent set of numerical parameters that are related to the equilibrium of hydrogen peroxide, uranyl ion and hydrogen ion.
Date: October 22, 1959
Creator: Gilpatrick, L. O.; Jolley, H. R.; Kelly, M. J.; Silverman, M. D. & Watson, G. M.
Partner: UNT Libraries Government Documents Department
open access

Programmers Manual: ORACLE Binary Internal Translator (ORBIT) - Algebraic Programming System for the ORACLE

Description: The present edition of the programmers manual for the ORACLE Binary Internal Translator has been completely revised and considerably expanded. At the same time, the Translator program itself has also undergone complete revision. The new version of ORBIT will accommodate programs written in accordance with the original instructions with minor exceptions.
Date: September 22, 1959
Creator: Grau, A. A.; Feliciano, M.; Caldwell, G. C.; Cooper, E. L.; Culkowski, A. & Harrison, J.
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department Monthly Record Report: September 1959

Description: This document details activities of the irradiation processing department during the month of September, 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: October 22, 1959
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
open access

Design of production test IP-297-A-FP, The effect of autoclave film damage on the incidence of groove pitting on X-8001 alloy fuel jackets

Description: The recent increase in the incidence of groove pitting on X-8001 clad fuel elements in the old reactors apparently refutes the earlier hypothesis that surface segregation of the secondary phase of this alloy was the primary cause of the unique, preferential attack sustained during irradiation. Components received within the past fifteen months have exhibited essentially none of the segregation. On the other hand, recent evidence suggests that localized penetration of the autoclave film on X-800… more
Date: December 22, 1959
Creator: Hall, R. E. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
open access

The Effect of Solution and Vessel Thermal Expansion on Volume Measurements in the Chemical Processing Department

Description: The major portion of transfers and inventory in the Chemical Processing Department are dependent on volume measurement. Good volume measurements are therefore essential to good SS material control. Considerable attention has been given to the volume problem especially on primary transfer points. Document HW-57888 discusses the biasing effect pf temperature on manometer oil. HW- 57866 given the procedure for vessel calibration. Other undocumented correspondence has discussed recent calibrations … more
Date: May 22, 1959
Creator: Johnson, W. R.
Partner: UNT Libraries Government Documents Department
open access

Control of Thorium Oxide Particle Size

Description: By carefully controlling the agitation, temperature, concentrations, and reagent addition rate, it was possible to produce a thorium oxide product within 0.3 mu of any selected size between 2.0 and 3.0 mu . The rate of addition of oxalic acid to a thorium nitrate solution was the variable used in the current series of tests. (auth)
Date: January 22, 1959
Creator: Johnsson, K. O. & Ellison, C. V.
Partner: UNT Libraries Government Documents Department
open access

Pilot Plant Preparation of Thorium and Thorium-Uranium Oxides

Description: Thorium oxide is formed by the calcination of thorium oxalate precipitated under carefully controlled conditions. Material is produced with mean particle diameters of 1 to 5 mu . Some of the thorium oxide had uranium added to it by decomposing uranyl carbonate on the thorium oxide followed by calcination. Most of the oxides prepared were calcined to 1000 deg C or more and size classified to remove particles greater than 10 mu . The oxides were prepared in 150-lb batches, with a complete cycle r… more
Date: December 22, 1959
Creator: Johnsson, K. O. & Winget, R. H.
Partner: UNT Libraries Government Documents Department
open access

Comparison of Fedal Monitor Readings With Radiochemical Sample Data

Description: The purpose of this test is to compare specific isotopic fission product activities with those of the neutron emitters which are monitored by the FEDAL System, and to obtain further information on the source of the unusual activity observed in the PWR reactor coolant.
Date: October 22, 1959
Creator: Jones, Edward
Partner: UNT Libraries Government Documents Department
open access

Control Rod Positions for Criticality

Description: The purpose of this test was to determine critical bank heights and bank worths for various rod configurations at normal Reactor Plant operating temperature and pressure.
Date: October 22, 1959
Creator: Jones, Edward
Partner: UNT Libraries Government Documents Department
open access

Internally Cooled Molten-Salt Reactors

Description: The initial and long-term nuclear characteristics of two internally cooled heterogeneous, graphite-moderated, two-region, molten-salt reactors have been studied. These reactors have doubling times of 22.5 years and 27.5 years. Methods of decreasing the doubling times by removing the Pa233 from the core and be increasing the specific power of the reactor are described.
Date: June 22, 1959
Creator: Lackey, M. E.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen