UNT Libraries Government Documents Department - 48 Matching Results

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709 Program for Reduction of Exponential Pile Data

Description: A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
Date: August 20, 1959
Creator: Matsumoto, D. D.
Item Type: Refine your search to only Report
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1A Reactor Inlet Hydraulic Valve Position Detector Temperature. Section I. Core I, Seed 1. Test Results DL-S-258-S, RNI-3

Description: The purpose of the test was to determine the internal temperature of the valve position detector for the 1A reactor inlet hydraulic valve with the plant at normal pressure and temperature and at power. The normal operating temperatures for the valve position detector on the 1A reactor inlet hydraulic valve range from a minimum of 287 F to a maximum of 294.7 F.
Date: November 20, 1959
Item Type: Refine your search to only Report
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An Automatic Water Deaeration System

Description: Laboratory studies involving fluid flow through porous media require use of fluids having low dissolved gas content. Water is the major fluid used in various and box model and soil permeability studies carried out by the Geochemical and Geophysical Research group. Tap water supplied to the 222-U Bldg. contains a large amount of dissolved air. Under the reduced pressure encountered during model studies, the air is released from solution and gradually clogs the pores of the sand or other porous m… more
Date: April 20, 1959
Creator: Raymond, J. R.
Item Type: Refine your search to only Report
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Centrifugal Casting of Aluminum-Uranium Alloys

Description: "Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 w/o uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced stilizing a pouring temperature of 2400 F, a heavy-walled steel cylinder rotating between 700 to 900 rpm for the mold and bottom-pouring technique employi… more
Date: July 20, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
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CENTRIFUGAL CASTING OF ALUMINUM-URANIUM ALLOYS

Description: Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 wt.% uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced utilizing a pouring temperature of 2400 ction prod- , a heavy-walled steel cylinder rotating between 700 and 900 rpm for the mold and a bottom-pouring tec… more
Date: July 20, 1959
Creator: Daniel, N.E.; Foster, E.L. Jr. & Dickerson, R.F.
Item Type: Refine your search to only Report
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Characterization of Surfactants in Aluminum-Uranium Fuel Reprocessing Solutions

Description: Surface active materials in aluminum nitrate-nitric acid fuel reprocessing solutions were characterized. Polymerized silica, zirconium- modified silica and soluble dibutyl phosphate species were found to contribute to stable emulsion formation. These surfactants were reduced in effectiveness by added acid. (auth)
Date: October 20, 1959
Creator: Cannon, R. D.
Item Type: Refine your search to only Report
open access

Chemical Processing Department Monthly Report: January 1959

Description: This report for January 1959, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.
Date: February 20, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
open access

Chemical Processing Department Monthly Report: February 1959

Description: This report for February 1959, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.
Date: March 20, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
open access

Chemical Processing Department monthly report for October 1959

Description: Pu output from separations plant was less than scheduled, but year-to- date production exceeded commitment by 4%. The Palm recovery run in Purex was the most successful to date. UO{sub 3} production and shipments met schedule. Purex had two pump failures. When Purex 1WW was centrifuged and treated to recover Ce, most of it remained in the centrifugate; only 14% was recovered. The prototype Pu ozonator in Redox performed well. Test runs on an acid precycle flowsheet and a proposed internal recyc… more
Date: November 20, 1959
Item Type: Refine your search to only Report
open access

Chemical Processing Department monthly report, March 1959

Description: Production of Pu, UO{sub 3}, and Pu metal exceeded forecasts. The 2nd attempt at Purex to recover Zr-Nb resulted in about 1/3 recovery, contaminated with about 1% of the Ce. Palm losses to Purex U product were eliminated, and the Pu content was reduced 5 to 10{times}. Routing the dissolver rinses into 3WB concentrator resulted into improved rinsing efficiency. Unclarified feed was processed through Purex HA column. In a test for using B in Redox, the B was routed completely to the waste; it was… more
Date: April 20, 1959
Item Type: Refine your search to only Report
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Corrosion of 2R-2 and 304 Stainless Steel Following the Turco-4501 Decontamination Process.

Description: The build up of contaminated film on the internal surfaces of high temperature in-reactor recirculating water loops has created serious radiation exposure problems to operational and maintenance personnel. A considerable amount of work has been applied to develop an effective decontamination process for the decontamination of these loops and their components.
Date: April 20, 1959
Creator: Larrick, A. P. & Lotsinger, R. J.
Item Type: Refine your search to only Report
open access

GAS-PRESSURE BONDING OF FLAT-PLATE FUEL ASSEMBLIES

Description: subscale fiat-plate fuel subassemblies measuring up to 2 by 2 by 20 in., incorporating 16 Zircaloy-2-clad uranium -zirconium fuel plates and 15 coolant channels, were successfully fabricated by the gas-pressurebonding process. Autoclave design, specimen-container configuration, and the design and preparation of specimen components were among the problems studied. Uneven heating of the bonding specimen, caused in part by convective heat transfer, was minimized by developing a special four-elemen… more
Date: January 20, 1959
Creator: Paprocki, S.J.; Hodge, E.S.; Boyer, C.B. & Getz, R.W.
Item Type: Refine your search to only Report
open access

HIGH FLUX ISOTOPE REACTOR PRELIMINARY DESIGN STUDY

Description: A comparison of possible types of research reactors for the production of transplutonium elements and other isotopes indicates that a flux-trap reactor consisting of a beryllium-reflecteds light-water-cooled annular fuel region surrounding a light-water island provides the required thermal neutron fluxes at minimum cost. The preliminary desigu of such a reactor was carried out on the basis of a parametric study of the effect of dimensions of the island and fuel regions heat removal rates, and f… more
Date: March 20, 1959
Creator: Lane, J. A.; Cheverton, R. D.; Claiborne, G. C.; Cole, T. E.; Gambill, W. R.; Gill, J. P. et al.
Item Type: Refine your search to only Report
open access

Incontamination of Pig Skin Contaminated With a Plutonium Solution

Description: Different methods of decontaminating plutonium contaminated skin were studied by contamination localized areas of pig skin and then testing the different decontamination methods. Results indicate that the most effective of the decontamination methods tested involved the application of a plastic adherent material to the skin and its later removal by peeling.
Date: August 20, 1959
Creator: George, L. A.; Dockum, H. L. & Bustad, L. K.
Item Type: Refine your search to only Report
open access

Investigation Of Windows And Shields For Neutron Point Sources

Description: An empirical approach for the evaluation of shielding materials for macrochemical manipulations of spontaneously fissioning heavy elements (curium and californium) has revealed interesting comparisons. High-density metal halide solutions were compared with lead glass and with rare earth glass for use as shielding windows. Laminated shields of lead-paraffin and uranium-paraffin were compared with water and with paraffin for shielding walls.
Date: May 20, 1959
Creator: Browne, Howard J.; Kaufmann, John A. & Garden, Nelson B.
Item Type: Refine your search to only Report
open access

Irradiation Processing Department monthly record report, January 1959

Description: This document details activities of the irradiation processing department during the month of January 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: February 20, 1959
Creator: Greninger, A. B.
Item Type: Refine your search to only Report
open access

Irradiation Processing Department Monthly Record Report: October 1959

Description: This document details activities of the irradiation processing department during the month of October, 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: November 20, 1959
Item Type: Refine your search to only Report
open access

Irradiation Processing Department monthly report, February 1959

Description: This document details activities of the irradiation processing department during the month of February 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: March 20, 1959
Item Type: Refine your search to only Report
open access

Irradiation program for candidate 105-N graphites

Description: Selection of new graphites for nuclear reactor moderator applications can be accomplished either by: (1) an evaluation of the behavior of untested materials processed by proven methods of manufacture when tested under conditions typical of the proposed application, or, (2) a development program exploring new materials, processes and environments which results in graphites meeting or exceeding design requirements. The latter approach is not easily adapted to construction schedules and therefore … more
Date: January 20, 1959
Creator: Woodruff, E. M.
Item Type: Refine your search to only Report
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