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100 Areas engineers technical activities report, December 1950

Description: Plant Assistance Group summaries are given for the B, D, F, H, and DR piles. The Engineering Development Group reports on: ball 3-X program, special field instruments, pile flux density measurements, magnesium inlet dummies, assistance to pile physics group, water survey program, boiling studies, slug temperature measurements, and the job status report for engineering development.
Date: January 2, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100 Areas technical activities report Engineers, January 1951

Description: Monthly reports are given for the B, D, DR, F and H piles. And the Engineering Development Group reports on the: Ball 3-X program, thermocouple slug irradiation and related studies, process water study, metallurgical and corrosion studies, analytical research, heat transfer and temperature effect experiment, assistance to pile physics group, miscellaneous development projects, and a job status report from Engineering Development.
Date: February 2, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100 Areas technical activities report, engineers - March 1951

Description: This is the monthly 100 areas technical activities report from the engineering division for the month of March 1951. It reports on engineering activities related directly to the different production reactors, and gives progress reports on various engineering projects which are in development by the engineering group.
Date: April 1, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100 Areas technical activities report - physics, July 1951

Description: This is the monthly 100 areas technical activities report for the physics group for the month of July 1951. This group was concerned with pile related studies. Work discussed includes neutron attenuation measurements in pile shielding test facilities, studies of physical properties of shielding materials (concrete), work on a xenon generator and separation facility, further development and shielding work for a neutron spectrometer, continued work on a magnetic spectrometer, and counting equipme… more
Date: August 3, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100 Areas technical activities report -- Physics, November 1951

Description: Activities discussed in this report are as follows: shielding studies; xenon generator; assay of xenon sample counting techniques; crystal diffraction neutron spectrometer; C{sup 12} cross sections measurements; magnetic spectrometer; scintillation spectroscopy; improved pile structure; criticality for the untamped 16 inch spherical reactor; exponential experiments; large scale pile structure; and operational pile physics.
Date: December 6, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Acenaphthene solvents for use in Building 313 Frost Test operation

Description: Acenaphtheno is a low-melting organic compound, C{sub 10}H{sub 6}(CH{sub 2}){sub 2}, used as a temperature indicating coating for slugs tested in the Frost Test induction coil. In preparation for this test, slugs are coated by spraying a 12 to 24 per cent by weight solution of acenaphthene in a high vapor pressure solvent on the rotating slug. The solvent evaporate leaving a thin, adherent coating of acenaphthene. This process is completely described in reference 1. To be entirely satisfactory … more
Date: June 26, 1951
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Addition of standard quantities of chemicals in certain reduction operations in the 234-5 Building

Description: A proposal by ``S`` Division that operations be simplified by adding fixed amounts of calcium and iodine in the reduction step as a time saving device has been investigated. Ten test runs in the 410--430 gram range have been compared with twenty normal runs made in this period. The average yields were 98.27% for the normal method and 98.26% for the test runs. No effect on individual yields by the variance in percent calcium and the iodine ratio was observed. Seventy percent of the runs normally… more
Date: September 28, 1951
Creator: Desposato, F.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of supernatants 234-5 Building

Description: The Pu in one batch (160 gms) is precipitated in a purification hood and waste supernatant is then transferred to the storage tank in one of the recovery hoods. Under normal process conditions a small amount of Pu remains in the supernatant. However, it is possible, though extremely unlikely, that the entire 160 grams would be transferred to the waste storage tank. The supernatants are transferred to an evaporator where they are concentrated. This evaporator has dimensions approximately the sam… more
Date: August 23, 1951
Creator: Gast, P.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An analysis of the suitability of various coring patterns for inclusion in ``C`` Reactor

Description: Preliminary meetings on coring of the graphite have been held with interested parties of the Technical and Production Divisions at which time the advantages and problems of coring were discussed. The advantages and the problems which must be surmounted in order to core have been presented to the working committee. A study of the means of accomplishing coring has been made considering only the central and maximum fringe coring. It is important that the minimum and maximum coring be established a… more
Date: April 13, 1951
Creator: Roy, G. M. & Andersen, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical results on leachings from Nutsche Filters

Description: This report describes results of an investigation to determine whether plutonium nitrates and lanthanum compounds were being entrained on the filter aid and filter block of the Nutsche Filters in Cell 2 of Bldg. 231. Leach samples were analyzed for La, Pu, phosphate, fluoride, Pu{sup 240}, and Am. From the data the authors concluded that the holdup on the Nutsche Filter is due to insoluble plutonium compounds either filtered from solution, or more likely, formed on the filter. These compounds w… more
Date: July 2, 1951
Creator: Barton, G.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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C-431 B -- Scope document

Description: This document describes the scope of the C-431-B Reactor Production Facility. In dealing with the broad phases of the project, it includes the Sections ``A`` (Scope Modifications) of the approved Design Criteria, modified to ensure correctness to date. Location of the facility has been set as shown on the site map in HDC-2101, designated site number one. Included in Project C-431-B are the 105-C Building, including within that building facilities previously located in the 1608 Building, a conta… more
Date: June 1, 1951
Creator: Hollister, H. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculated and observed P-10 production in H-10

Description: Recently three H-10 tubes (2,772, 2,176, 3,673) have been removed and the tritium and other gases have been extracted from the Z slugs. It is of interest to compare the calculated volumes of gases with the amounts obtained in these extractions. The comparison is given in this paper. The reasons for the large disagreement are not known at present. As pointed out below, the weakest part of the calculation is the knowledge of the exposure which these Z slugs have received. It is possible that some… more
Date: January 12, 1951
Creator: Ozeroff, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Capacity survey -- Separations Division

Description: Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentrat… more
Date: June 28, 1951
Creator: Frame, J. M. & Tomlinson, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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