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in publisher: "Mallinckrodt Chemical Works Saint Louis, Mo."  
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Research and Development Progress Report

Description: "The St. Louis Refinery produced its first UO3 and UO2 in 1942, and its first UF4 and U metal in 1943. The accent has always been on production, and the function of the extremely small research and development groups has been to aid the production units in their job. ... Recently, there has been a growing realization of the need for a broader and more detailed knowledge of both the chemical and technological aspects of all phases of work. ... This is the first of a series of quarterly progress… more
Date: October 15, 1952
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HAZARDS SUMMARY REPORT FOR THE ARMY PACKAGE POWER REACTOR

Description: The APPR-I is described and the various hazards are reviewed. Because of the reactor's location near the nation's Capitol, containment is of the utmost importance. The maximum energy release in any possible accident is 7.4 million Btu's which is completely contained within a 7/8 inch thick steel cylindrical shell with hemispherical ends. The vapor container is 60 ft high and 32 ft in diameter and is lined on the inside with 2 ft of reinforced concrete which provides missile prote… more
Date: July 27, 1955
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ionium Recovery Plant Design Report: Topical Report

Description: This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
Date: April 15, 1959
Creator: Edwards, R. M.; Fariss, R. H. & Werkema, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE CORROSION RESISTANCE OF SEVERAL ALLOYS IN AN HF-H$sub 2$O ATMOSPHERE AT HIGH TEMPERATURES

Description: Tests indicate that of the various alloys tssted for corrosion resistance when exposed 10 an HF-HP atmosphere at 1070 F, the Cr-Ni alloys, as a group, give the best corrosion resistance where strength at high temperature is desired. Other alloys have given excellent results but the lack of strength at the higher temperatures or cost, is against their use in production equipment. (auth)
Date: January 22, 1952
Creator: Ritchie, C.F. & Teter, E.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Process Development Quarterly Report. Part 2. Pilot Plant Work

Description: Efficiency of the pilot plant pumper-decanters was greatly improved by the maintenance of interfaccs. The low efficiency of the D-3 pumper-decanter in the plant could be substantially raised by an interface to prevent backmixing. A review of refinery performance, based on a correlation of wash raffinate density with extract uranium saturation showed that high-thorium product resulted from low extract saturation. Tributyl phosphate recovery by hexane stripping of raffinate can be greatly improve… more
Date: August 1, 1959
Creator: Shepardson, J. U. & Nelson, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FEASIBILITY OF PARTIAL CHEMICAL CONTROL FOR THE SM-2. SM-2 (FORMERLY APPR- 1B) DESIGN PROGRAM, TASK 12-CHEMICAL CONTROL

Description: Chemical control of the SM-2 was evaluated both as a partial substitute for burnable poison in the fuel element meat and as a means of improving plant performance. Based on a review of existing information, boric acid was chosen as the reference soluble poison. It was shown that 60% of the burnable B/sup 10/ in the fuel element matrix could be replaced by soluble B/sup 10/ in the coolant without impairing plant stability during load transients. The feasibility of improving power distribution an… more
Date: May 15, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A PROCESS FOR CONTROLLING INSOLUBLE URANIUM IN ORE CONCENTRATES I. LABORATORY INVESTIGATION

Description: A process has been developed for converting nitricacid-insoluble uranium in ore concentrates into soluble form. Ore concentrates are treated with a reducing agent such ss carbon monoxide or hydrogen at temperatures or 670 to 730 C. In the laboratory, retention times nsoluble uranium vary inversely with the concentration or the reducing agent. Laboratory studies leading to the development of the process are reported. (auth)
Date: February 1, 1959
Creator: Lang, G.P.; Nelson, E.N. & Kuhlman, C.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRIMARY SHIELDING CALCULATIONS ON THE IBM 650 (ROC CODES)

Description: Four programs written for the IBM 650 to calculate the gamma dose rates in the primary shielding of thermal reactors are described. Their functions are outlined as follows: Program 651-calculates the core attenuation coefficient and equivalent core gamma volumetric source values for a specific core. Program 652- calculates the activation gamma source data in the shield and prepares tabular data in machine storage for Programs 653 and 654. Program 653- calculates the gamma dose rates in the shie… more
Date: October 15, 1958
Creator: Rosen, S. S.; Oby, P. V. & Caton, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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IBM 650 COMPUTER--PROGRAM NUMBER 655 COLLATION OF ROC CODE OUTPUT

Description: Using the output of programs 653 and 654, each card of which contains the dose information for one dose point at one energy, program 655 produces the sum of the dose values of all energies for one dose point. Program details are given including 650 input and output formats, operating instructions, and guides. (auth)
Date: December 19, 1958
Creator: Stueck, C.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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