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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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Radiochemistry of uranium, neptunium and plutonium: an updating

Description: This report presents some procedures used in the radiochemical isolation, purification and/or analysis of uranium, neptunium, and plutonium. In this update of the procedures, we have not attempted to discuss the developments in the chemistry of U, Np, and Pu but have restricted the report to the newer procedures, most of which have resulted from the increased emphasis in environmental concern which requires analysis of extremely small amounts of the actinide element in quite complex matrices. T… more
Date: February 1, 1986
Creator: Roberts, R. A.; Choppin, G. R. & Wild, J. F.
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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A Study of the Distribution of Impurities in the Extraction of Uranyl Nitrate with Ether from Aqueous Solutions

Description: Early in 1942 it had been found on a laboratory scale that certain impurities such as the Rare Earths were removed by small water washes from an ether solution of Uranyl Nitrate. It was hoped that in the large production units to be constructed that the water soluble impurities would all be washed out by the time the radioactive Thorium had been removed, so that the decrease in radioactivity could be used as an index of the amount of all kinds of impurity remaining in the ether layer. Experienc… more
Date: April 1, 1946
Creator: Conard, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Structural Testing of SM-2 Fuel Elements

Description: Ability of the originally designed SM-2 stainless steel fuel elements to withstand static transverse pressure gradients of normal reactor operetion was investigated. Fourteen simulated original SM-2 type fuel elements by Tungsten inert gas (TIG) and electric resistance welding processes were subjected to pressure gradients to 6 psi and measured for deflection during stress and distortion after stress. Tests provided a basis for selecting a reference SM-2 fuel-element design and established a me… more
Date: September 29, 1960
Creator: Coleman, F.G. Jr. & Herbert, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SM-2 SINGLE ELEMENT FINAL TEST REPORT

Description: Tests were conducted on an SM-2 control-rod assembly and stationary element to determine channel-to-channel coolant flow distribution and static pressure drops across both the control-rod assembly and stationary element, and to select proper top and bottom core support configurations necessary to bring stationary element channel-to-channel flow distribution within prescribed limits of plus or minus 6% of element average. Results showed control-rod channel-to- channel flow distribution was +7.0%… more
Date: October 28, 1960
Creator: Krause, P.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THERMAL STRESS TESTING OF SM-2 FUEL ELEMENTS. Interim Technical Report for January 1, 1959 to January 1, 1960

Description: Thermal stress testing was performed on two fuel plates, one cut from a brazed SM-1 dummy fuel element and the other from a TIG Welded SM-2 reference element. The test specimens were subjected to transverse temperature differences of up to 200 deg F, and distortion and strain at various locations were measured. The effect of the thermal stress was to increase the amplitude of original distortions. Adddtional distortions due to thermal stress were proportional to temperature differential and to … more
Date: October 31, 1960
Creator: Christenson, J.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SUMMARY OF REACTOR DESIGN INFORMATION FROM THREE YEARS' OPERATION OF A SMALL PWR

Description: Reactor design information obtained from 3 years' operation of a small pressurized-water reactor, the SM-1 (formerly APPR-l), is presented and discussed. The SM-1 reactor, designed to produce 10 Mw(t) power, employs fully enriched uranium fuel in the form of UO/sub 2/ dispersed in stainless-steel fuel plates. The reactor is cooled by water at 1200 psia and mean temperature of 44) deg F. Core-physics measurements were performed of temperature coefficient, pressure coefficient, rod calibration, s… more
Date: September 1, 1960
Creator: Gallagher, J.G.
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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Processing of Special Metal for Hanford

Description: The object of this project is to reduce the impurities and raise the density of rejected slugs and briquetted turnings from these slugs by recasting the material. Summary and conclusions are (1) slugs and briquettes made from turnings produced when these slugs were machined can be recast with great improvement in quality; (2) casting this material is quite hard on graphite crucibles, but a long-range program might point the way to better graphite usage; (3) this metal run alone gives fair yield… more
Date: March 10, 1947
Creator: Oppold, William A.
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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