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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
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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
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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
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Reactivity Control By Addition Of Neutron Poisons To Slurry Reactors

Description: Calculations show that slurry fueled reactors may be maintained subcritical at arbitrary concentrations and at reactor temperatures above a specified minimum by addition of a soluble neutron poison to the slurry.
Date: December 22, 1959
Creator: Pearson, R. L.; Prince, B. E.; Jeffrey, D. W. & Brassert, W. L.
Partner: UNT Libraries Government Documents Department
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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
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3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples

Description: The calculation of shielding the thickness for plutonium is complicated by the many different energies represented in the gamma radiation emitted during decay of the plutonium isotopes. Dose rate predictions are also frequently confused by gamma from varying content of fission product impurities in the plutonium, as well as other gamma radiation induced through alpha and neutron particle absorption within the source material or its environment. After assumptions are made for these many factors… more
Date: October 22, 1959
Creator: Moulthrop, H. A.
Partner: UNT Libraries Government Documents Department
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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
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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
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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
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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
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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
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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
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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
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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
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Periodic Radiation Survey of Reactor Plant Container and Components After Shutdown "A" Survey

Description: The purpose of this survey is to determine the general area radiation level in the Boiler Compartments using Channel 5 of the Operational Radiation Monitoring System. This report includes the fourth performance test results.
Date: October 22, 1959
Creator: Nelson, Ralph L.; George, John R. & Jones, Edward
Partner: UNT Libraries Government Documents Department
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Protection of Carbon Steel from Atmospheric Corrosion

Description: The NPR design calls for carbon steel to be the major constituent in the reactor coolant piping system. The piping and its associated fittings will, in all likelihood, be exposed to atmospheric weather conditions during the period of reactor construction. This type of exposure causes rusting. From experience gained during the startup of KER Loop 1 it is expected that there will be initially high NPR coolant activity levels. The high activity during the startup of KER Loop 1 was partially caused… more
Date: October 22, 1959
Creator: Perrigo, Lyle D., Jr. & Moles, R. G.
Partner: UNT Libraries Government Documents Department
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Notes on Heat Transfer in the ORR Core at Powers Greater Than 20 Mw

Description: One of the problems being considered in anticipation of raising the power of the ORR is the possibility of nucleate boiling due to excessive heat fluxes. This note is an attempt to analyze some of the worst conditions of a known core along with extrapolation to higher powers.
Date: September 22, 1959
Creator: Wett, J. F.
Partner: UNT Libraries Government Documents Department
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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
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Soil Column Studies with Radiostrontium I. Effects of Temperature and of Species of Accompanying Ion

Description: Soil chemistry studies have been carried on at Hanford for a number of years in support of the disposal of low and intermediate level liquid wastes to the ground. Equilibrium type experiments were carried out to investigate the mechanisms of the reactions of Sr, Cs, and rare earth ions with soils (1, 3, 4, 5). Experiments were also conducted with simulated and actual wastes in soil columns and an empirical method was developed for prediction of radionuclide breakthrough from ground disposal fac… more
Date: September 22, 1959
Creator: Nelson, J. L.
Partner: UNT Libraries Government Documents Department
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Temperatures and Thermal Stresses in Hexagonal Tubes and Pierced Plates With Internal Heat Sources

Description: From abstract: "Steady temperatures and thermal stresses are determined for long hexagonal tubes having round holes for the case of uniform internal heat generation and a fluid-cooled inside surface. Thermal stresses are also determined for thick plates pierced by holes on an equilateral triangular pattern and for hexagonal tubes having a hexagonal hole with rounded inside corners. Stresses in the end regions of tubes are also investigated."
Date: September 22, 1959
Creator: Meuser, Robert B.
Partner: UNT Libraries Government Documents Department
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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
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Chemical Processing Department monthly report, June 1959

Description: Production of Pu from separations plants and output of unfabricated Pu exceeded commitments. Purex plant set a new record high for U processed. Production and shipments of UO{sub 3} met schedules. Purex solvent extraction battery performed below normal, probably because of poor solvent quality. NaOH addition to Redox coating removal waste is being reduced. A 3fold improvement in Recuplex product Al impurity was achieved by means of a specific gravity difference > 0.15 between dilute aqueous fee… more
Date: July 22, 1959
Creator: MacCready, W. K.
Partner: UNT Libraries Government Documents Department
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A Microspark Apparatus for the Study of Inclusions in Metals

Description: A study of metallurgical problems resulting from variation in grain boundaries, bonding layers, and inclusions in metals and alloys has become increasingly important over the past several years. To keep pace with and aid in these studies, several new techniques have been developed in emission and X-ray spectroscopy. In X-ray, areas as smalls as one square micron can be studied by making them targets for a focused electron beam and observing the X-rays emitted (5,2). Such an instrument would be … more
Date: July 22, 1959
Creator: Smith, F. M.
Partner: UNT Libraries Government Documents Department
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