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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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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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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

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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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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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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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
open access

190-C pump capacity

Description: The purpose of this document is to update 190-C pump capacity information previous released in HW-52449{sup 1} and HW-58580{sup 2}. Improvements in motor cooling has resulted in raising the previous 3500 HP limit to 3660 HP{sup 3} thus increasing total pumping capacity.
Date: June 22, 1959
Creator: Watson, D. F.
Partner: UNT Libraries Government Documents Department
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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
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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
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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
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Internally Cooled Molten-Salt Reactors

Description: The initial and long-term nuclear characteristics of two internally cooled heteroingeneous graphite-moderated two-region molten-salt reactors were studied. The reactors have doubling times of 22.5 and 27.5 years. Methods of decreasing the doubling times by removing the Pa/sup 233/ from the core and by increasing the specific power of the reactor are described. (auth)
Date: June 22, 1959
Creator: Lackey, M. E.
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
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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
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