Technical Report Archive & Image Library (TRAIL) - 167 Matching Results

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Reactor Engineering Division Quarterly Report September 1, 1952 through November 30, 1952

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: December 15, 1952
Creator: Argonne National Laboratory. Reactor Engineering Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Engineering Division Quarterly Report September 1, 1953 through November 30, 1953

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: December 15, 1953
Creator: Argonne National Laboratory. Reactor Engineering Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Engineering Division Quarterly Report June 1, 1953 through August 31, 1953

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs (including the Power Breeder Reactor (PBR) and the Central Station Water Reactor (CSWR)), designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: September 15, 1953
Creator: Argonne National Laboratory. Reactor Enginneering Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Improved Continuous Ether Extractor for the Determination of Uranium in Dissolver Solutions

Description: An improved continuous ether extractor is described. The modifications include a means of safely disposing of the active raffinate and a means of positivity checking the raffinate for completeness of uranium extraction. The results obtained on synthetic samples and on dissolver solutions are given. This work was undertaken because of a need for the determination of uranium in dissolver solutions with an accuracy of 0.1 per cent. After a review of available methods it was decided that a gravimet… more
Date: August 27, 1953
Creator: Bane, R. W. & Jensen, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Helium Leak Detector Test for Hanford And Savannah River Fuel Slugs

Description: The Helium Leak Detector Test provides a method for detecting the presence of minute holes, cracks, fissures, etc. in the aluminum jackets of Hanford and Savannah River reactor fuel slugs which would allow moisture to penetrate to the uranium during reactor operation.
Date: December 31, 1952
Creator: Barnes, A. H.; Smith, F. A. & Wimunc, E. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Roll Cladding of Uranium-Niobium Alloys for Plate Type Fuel Elements

Description: The feasibility of cladding plate type, corrosion resistant uranium-niobium fuel elements with Zircaloy-II by roll bonding has been demonstrated. Plates with cores of uranium alloyed with 3 w/o and 6 w/o Nb intended for irradiation testing in a high temperature water test loop in the MTR have been finished withing specified tolerances. The preparation of cladding billet core and clad components and the assembly of billets by enclosing cores in welded Zircaloy-II jackets can be readily accomplis… more
Date: December 1953
Creator: Bean, C. H. & Macherey, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Report on the Argonne-Oak Ridge Digital Computer

Description: Report issued by the Argonne National Laboratory discussing a progress report on the Argonne-Oak Ridge digital computer. This report is an interim report, whose primary value is that it has forced those engaged in the work to give concrete expression to what they have been doing and thinking about up to this point. This report includes tables, illustrations, and photographs.
Date: March 5, 1951
Creator: Birge, W. A.; Burdette, E. W.; Burks, A. W.; Chu, J. C.; Flanders, D. A.; Jacobsohn, D. H. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparative Analysis of ANL High Purity Uranium

Description: In the course of the development at Argonne of high purity uranium metal in ingot form, some questions arose as to the validity of the chemical analyses of some of the impurities (particularly those for carbon, boron, and silicon), with one analytical laboratory reporting concentrations in some instances of an order of magnitude greater than another laboratory. Since the low concentrations of impurities in this material involved, in some cases, the development of modified analytical procedures … more
Date: September 24, 1953
Creator: Blumenthal, B. & Chiswik, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electronic Distribution Functions and Thermodynamic Properties at High Temperatures

Description: Report issued by the Argonne National Laboratory discussing the thermodynamics and electronic distribution of high temperatures. As stated in the introduction, "in the present paper, a model for computing is described which takes into account in detail the interactions between bound electrons and the average interaction of the bound electrons with the free ones" (p. 4). This report includes tables, and illustrations.
Date: May 1953
Creator: Brachman, Malcolm K. & Meyerott, Roland E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion and Stability Tests on Chemical Poisons in Higher-Temperature Water

Description: Corrosion-stability tests have been made in static autoclaves at 500 and 600F on solutions of compounds having high neutron cross sections to evaluate their usefulness for shutdown purposes. The only compound tested which appeared to be completely stable in 600F water was boric acid. Limited corrosion data did not show it to cause excessive corrosion of zirconium or stainless steel.
Date: September 1, 1953
Creator: Breden, Calvin Rudolph, 1901- & Abers, Alma
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Soluble Poisons in Reactor Control

Description: Theoretical and experimental investigations of the use of soluble poisons (neutron absorbers) to supplement mechanical control rods are summarized. Experimental evaluation of poisons of interest includes in-pile and out-of-pile tests simulating anticipated reactor operating conditions. Other phases of the investigation included methods of poison injection, removal, and cleanup of poison-diluted reactor systems, as well as studies to evaluate possible application of soluble poison control in exi… more
Date: November 1955
Creator: Breden, Calvin Rudolph, 1901-; Brown, W. S. & Sivetz, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Review of ZPR-1 Accidental Transient - the Power Excursion, Exposures, and Clinical Data

Description: On June 2, 1952, 15:52 hours, a large reactivity change was made manually in a ZPR-1 assembly causing a power excursion of about one kwh, which resulted in damage to the reactor core components and radiation exposure of some of the operating personnel to perhaps several rep. None of the contributing causes is reviewed here nor are the measures which were taken to reduce the probability of a recurrence discussed since these are considered administrative matters beyond the scope of this technical… more
Date: January 26, 1953
Creator: Brittan, R. O.; Hasterlik, R. J.; Marinelli, L. D. & Thalgott, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility Report on Fast Exponential Experiment

Description: The general program established at Argonne National Laboratory in connection with the Fast Power Breeder Reactor (PBR) includes performance of exponential experiments on assemblies having compositions which may exist in the reactor core. This report deals with that phase of the program known as the Fast Exponential Experiment which may be described very briefly as follows. An assembly of fissile (U-235) and fertile material (too small to be self-critical) intermixed with poisons (such as are en… more
Date: June 10, 1953
Creator: Brittan, R. O.; Hummel H. H.; Livingood, John J. (John Jacob), 1903-; Martens, F. H. & Spinrad, Bernard I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952

Description: Report issued by the Argonne National Laboratory discussing the Conference on the Toxicity of Carbon 14. At the outset of the meeting it was emphasized that the group was brought together to discuss work which had a bearing on the toxicity of C14 compounds used either clinically or industrially, and the hope was expressed that the group might be able to reach some conclusions on these matters. This report includes tables.
Date: March 1952
Creator: Brues, A. M. & Buchanan, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments

Description: Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and … more
Date: September 1967
Creator: Bryant, Lawrence T.; Amiot, Lawrence W.; Dickerman, Charles E. & Stephany, William P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

Description: Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date: July 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and Testing of a High-Heat Flux Electron-Bombardment Heater

Description: Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.
Date: March 1968
Creator: Carlson, R. D. & Holtz, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Regeneration Factor as a Function of Time in a Th232 - U235 Thermal Reactor

Description: This technical report is concerned with a theoretical investigation of the variation of the regeneration factor [gamma] in a Th232 - U235 thermal reactor. The abundances of the significant isotopes in the thorium-uranium cycle have been derived as a function of irradiation time at constant reactor power. The change in [gamma] as a function of irradiation time at constant power was calculated for combinations of enrichment and resonance escape probability considered likely to exist in a thermal … more
Date: September 1954
Creator: Carter, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity as a Function of Irradiation Time in Thermal Reactors

Description: Equations governing the variation of U235. U238, Pu239, Pu240, and Pu241 have been derived and their solutions plotted as a function of irradiation time. The initial U235 content of the uranium was varied from 0.5% to 2.0%. The range of conversion ratios was from 0.5 to 1.2. The irradiation was from 0 to 20,000 mwd/ton of fuel. Since a range of initial conversion ratios is associated with each value of enrichment, a solution results in a family of curves for each isotope, and, since the range o… more
Date: December 1953
Creator: Carter, J. C. & West, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Preferred Orientation and Grain Size On Dimensional Stability of Uranium on Thermal Cycling and Irradiation : Final Report -- Metallurgy Program 5.1.7

Description: The growth of alpha-rolled uranium rods on thermal cycling has been shown to depend on both preferred orientation and grain size. Preferred orientation appears to be a necessary condition for growth to occur; the extent of the growth depends upon the sharpness and type of texture developed and on the grain size. The highest growth rates occur in specimens with highly developed textures coupled with small grain sizes. The growth rates increase with cycling level, particularly in specimens of lar… more
Date: March 1956
Creator: Chiswik, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Growth Rates and Microstructural Characteristics of 300 C Rolled Uranium Rods on Thermal Cycling

Description: The thermal cycling growth and the accompanying metallographic changes were studied in 300 [degree] C rolled uranium rods up to 3000 cycles. The growth rate was found to decrease at the higher cycling levels. Project-grade material developed substantial porosity during cycling; high purity material showed no evidence of porosity.
Date: May 1956
Creator: Chiswik, H. H. & Mayfield, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physical and Mechanical Properties of Some Aluminum-Lithium Alloys

Description: The results of this study are tabulated in Summary Tables A and B below. For the most part, these values were read from smoothed curves drawn thru the plotted experimental data. The values for aluminum (i.e., 0 w/o Li) were taken from the 1948 Edition of the ASM Metals Handbook. The room temperature properties are reported for lithium contents of 0, 3.5, 7 and 10 weight per cent. In the case of the high temperature properties, there were insufficient data to allow extrapolation and interpolatio… more
Date: November 18, 1952
Creator: Chiswik, H. H.; Lehrer, W. M. & Rideout, S. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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