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ALPR Preliminary Design Study (Argonne Low Power Reactor) Phase 1

Description: A preliminary design study, Phase I of the ALPR project, has been made in accordance with the Army Reactors Branch specifications for a nuclear "package" power plant with a 200-260-kw electric and 400 kw heating capacity. The plant is to be installed at the Idaho Reactor Testing Station as a prototype for remote arctic installations. The "conventional" power plant as well as the exterior reactor components are described in the accompanying report and cost estimate by Pioneer Service and Engineeā€¦ more
Date: April 20, 1956
Creator: Treshow, M.; Pearlman, H.; Rossin, D. & Shaftman, D.
Partner: UNT Libraries Government Documents Department
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Annual Report 1961

Description: This seventh Annual Report is a summary of some of the progress in scientific and engineering research and development carried on at Argonne National Laboratory during 1961. As is customary in this series, only those portions of the total program that have reached such a stage that they may be of general interest are recorded. Thus, a comparison with the Annual Reports for 1959 (ANL-6125) and for 1960 (ANL-6275) will reveal the description of a generally different set of scientific activities. ā€¦ more
Date: 1961
Creator: Argonne National Laboratory (ANL)
Partner: UNT Libraries Government Documents Department
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Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature

Description: This report describes corrosion rate of uranium in hydrogen-saturated water appears to be constant with respect to time after a brief induction period and to involve only one type of over-all reaction, in which pitting effects are slight or nonexistent.
Date: May 14, 1952
Creator: McWhirter, J. W. & Draley, Joseph Edward, 1919-
Partner: UNT Libraries Government Documents Department
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Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Description: Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.
Partner: UNT Libraries Government Documents Department
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Argonne National Laboratory Idaho Division Summary Report: July-September, 1960

Description: Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
Date: 1960
Creator: Argonne National Laboratory. Idaho Division.
Partner: UNT Libraries Government Documents Department
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Atomic Energy Commission Division of Reactor Development Reactor Information Meeting. Part VI, Processing; October 7, 8, 9, 1953

Description: On October 7, 8, and 9, 1953, the Atomic Energy Commission Division of Reactor Development held a reactor information meeting at the Argonne National Laboratory. The objective of the meeting was exchange of information among people actively concerned with the design of reactors for power to the end that the power reactor program would move more speedily and more economically to another milestone of success. In this volume all the papers presented at the meeting are listed. Copies are given of tā€¦ more
Date: October 1953
Creator: Lawroski, Stephen
Partner: UNT Libraries Government Documents Department
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Attack on Uranium by Lithium at 600 C

Description: The tests described in this report were static tests devised to afford a basis for a quick evaluation of the resistance of uranium to attack by lithium. The work was done at the same time as the tests of beryllium, thorium, and various engineering metals in lithium (described in ANL-4990); but the results with uranium are given in the present classified report so that the results of the other tests can be published as an unclassified document. The procedure for carrying out the tests is describā€¦ more
Date: October 13, 1950
Creator: Wilkinson, Walter D. & Yaggee, Frank L.
Partner: UNT Libraries Government Documents Department
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Autoclave Testing of Mechanically Jacketed Thorium Slugs In Water

Description: Water corrosion tests on mechanically jacketed and pinholed thorium slugs show that these slugs fail in a manner similar to that observed for mechanically jacketed and tested uranium slugs. The proposed mechanism for the water corrosion of these jacketed slugs is analogous to the water corrosion mechanism of jacketed uranium slugs presented in the project lecture. A bare thorium slug appeared to be more resistant to corrosion by water than a mechanically jacketed slug during the first half of tā€¦ more
Date: January 29, 1953
Creator: Yaggee, Frank L.
Partner: UNT Libraries Government Documents Department
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Calculations on U235 Fission Product Decay Chains

Description: Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
Date: May 1952
Creator: Faller, I. L.; Chapman, T. S. & West, J. M.
Partner: UNT Libraries Government Documents Department
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A Capsule Design for Experimental High-Flux Irradiations Of Fuel Materials

Description: New reactors presently in design or construction stages, as well as revised operating procedures for existing reactors, have shown an increasing emphasis on extending the exposure time of the reactor fuel elements. However, operating experience at Hanford, as at other installations, has demonstrated that as the amount of burn-up in uranium metal is increased an increase is also noted in operational difficulties resulting from the dimensional behavior of the fuel. During reactor irradiation uranā€¦ more
Date: October 6, 1952
Creator: Kittel, J. Howard & Tedeschi, P.
Partner: UNT Libraries Government Documents Department
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Casting of Blanket Bricks, Ring, Plug, and Control Rods for the Experimental Breeder Reactor (CP-4)

Description: The cup assembly of the Experimental Breeder Reactor (EBR) consists of blanket bricks, inner rings, and safety plug, all of natural uranium. The design of the finish machined brick is shown in Figure 1. These pie shaped bricks when stacked together, 12 bricks arranged in circular form and stacked seven rings high, comprise the cylindrical portion of the outer blanket, 17.875" I.D. x 30.875" O.D. after machining and canning. The inner ring, which is shown in Figure 2, fits inside the bottom layeā€¦ more
Date: March 19, 1953
Creator: Macherey, Robert E.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report

Description: Measurement of radioactive carry-over was made on borax III operating at 300 psig and at power levels ranging from 4 to 14 mv. Decontamination factors of from 1.5 x 104 (at 14 mv) were obtained. These data are in essential agreement with those predicted by previous laboratory experimental work.
Date: May 2, 1956
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report for January, February, and March 1957

Description: A fused fluoride process for dissolution of zirconium-uranium fuel alloys is being developed. The alloy is dissolved in an equimolar sodium fluoride-zirconium fluoride melt at 600Ā°C by sparging the system with hydrogen fluoride. The uranium is volatilized from the melt as the hexafluoride by a sparging operation with fluorine or bromine pentafluoride vapor. This product is then decontaminated and purified by fractional distillation.
Date: July 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report for January, February, and March 1958

Description: Development work was continued on the fused fluoride process for the recovery of enriched uranium from zirconium-matrix fuel alloys. The alloy is dissolved by immersing it in molten sodium fluoride-zirconium fluoride at 600Ā°C and passing hydrogen fluoride vapor through the system.The dissolved uranium tetrafluoride in the melt is then volatilized as uranium hexafluoride by sparging with fluorine. The uranium hexafluoride product is purified and decontaminated by fractional distillation. Additioā€¦ more
Date: June 1958
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report : January, February, And March 1953

Description: Dissolution of the large number of samples obtained from the natural uranium blanket of the Experimental Breeder Reactor after approximately 485,000 kw.-hr. of operation has been completed, and analysis of these samples for uranium consumed and plutonium formed is well along. An attempt is being made to distinguish quantitatively between uranium-238 and uranium-235 fission in the blanket area by determining the ratio of ruthenium-106 to cesium-137 in the fission products.
Date: May 12, 1953
Creator: Lawroski, Stephen & Stevenson, C. E.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report January, February, and March, 1954

Description: Progress is reported on (1) direct cycle boiling reactor studies, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) fluidization studies, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: May 1, 1954
Creator: Lawroski, Stephen; Rodger, W. A. & Vogel, R. C., 1928-
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report July, August, and September, 1956

Description: Additional runs have been made in the six-inch, continuous-flow mixing chamber to study the rate of mass transfer between isobutanol and water. These runs were inconclusive because the effluents were mutually saturated. A new four-inch cell has been designed and is being fabricated; this will permit a reduction in the time available for mass transfer. Consideration has been given to other liquid pairs which may transfer more slowly than isobutanol-water. The system nitrobenzene-ethylene glycol ā€¦ more
Date: December 1956
Creator: Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report July, August, and September, 1957

Description: Development work continued on a fused salt process for the recovery of uranium from zirconium-matrix fuel alloys. The fuel is dissolved in a sodium fluoride-zirconium fluoride melt at 600Ā°C by hydrogen fluoride sparging. The melt is then sparged with fluorine gas which volatilizes the dissolved uranium as the hexafluoride. The final decontamination and purification of the uranium hexafluoride are accomplished by fractional distillation. The testing of graphite as a container material for the hyā€¦ more
Date: December 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report October, November, and December, 1953

Description: Progress is reported on (1) experimental breeder reactor program, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) denitration of uranyl nitrate in a fluidized bed, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: January 1, 1954
Creator: Lawroski, Stephen & Stevenson, C. E.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report October, November, and December, 1956

Description: A final series of runs was made in a four-inch continuous-flow mixing chamber to study the transfer of isobutanol into water and nitrobenzene into ethylene glycol. Satisfactory techniques were developed to provide for the rapid analysis of these systems. In addition, a light-scattering correlation was prepared to provide a measure of the interfacial area of the yellow-colored nitrobenzene-ethylene glycol mixtures.
Date: March 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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