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The Thermal Neutron Cross Section Of 9.2h Xe135 : Supplement to Report CP-2782

Description: In this report it reviews a possible declassification of the content of report CP-2782 (February 15, 1945) that presents the data of the most careful measurements of the thermal neutron cross section of 9.2h Xe135 and re-evaluation of the particular methods of measuring neutron flux employed in this experiment had been made for other purposes.
Date: September 12, 1952
Creator: Freedman, Melvin S. (Melvin Sleen), 1915-
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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Preferred Orientation in 300 C Rolled and in Recrystallized Uranium Sheet

Description: The rolling and recrystallization textures in 300 C rolled uranium sheet were investigated using a Geiger counter diffractometer with the modified Schulz reflection technique. Seven sections of sheet material were used in order to obtain sufficient data for quantitative pole figures by the reflection technique. A special integrating specimen table was used for obtaining and recording the data atomically.
Date: September 15, 1953
Creator: Mueller, Melvin Henry, 1918-; Knott, Harold W. & Beck, Paul A. (Paul Adams), 1908-
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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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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The Development of Equipment and Methods for Centrifugally Casting Reactor Fuel Slugs

Description: This technical report describes the design and construction of equipment and the development of methods for multiple mold, centrifugal casting of reactor fuel slugs. Advantages of the centrifugal casting method over the conventional fabrication methods were found to be (1) fewer operations, (2) fewer and more easily recovered residues, (3) less expensive equipment, and (4) the production of fuel slugs in shapes and in alloys not well adapted to other methods of manufacture. The method consisted… more
Date: September 29, 1953
Creator: Shuck, Arthur B., 1918-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report July, August, and September 1953

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion,
Date: September 30, 1953
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
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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Selected Values of the Physical Properties of Various Materials

Description: Report issued by the Argonne National Laboratory discussing selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis. In most cases, values for thermal conductivity specific heat, density, viscosity, and Prandtl numbers are given as functions of temperature. This report includes tables, and illustrations.
Date: September 1958
Creator: Tebo, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Terminal Report on the Mighty Mouse High-Flux Research Reactor Project

Description: From Introduction: "More specifically, it describes the basic reactor complex, the problems involved, the various approaches pursued, the present status and estimated cost of the project, along with recommendations for future research and development essential to the successful culmination of the project."
Date: September 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Dickson, R. F.; Heineman, J. B.; Kelber, C. N. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Summary Report on the Juggernaut Reactor

Description: Report issued by the Argonne National Laboratory over design studies conducted on the Juggernaut reactor. Design processes, and methods are presented and discussed. This report includes tables, illustrations, and photographs.
Date: September 1962
Creator: Folkrod, J. R.; Ember, G.; Kolb, W.; Saluja, J. & Moon, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Breeding-Gain Specimens for EBR-I Core IV

Description: Report issued by the Argonne National Laboratory over studies conducted on uranium and plutonium specimens used in fuel rods. The results are presented and discussed. This report includes tables, illustrations, and photographs.
Date: September 1963
Creator: Shuck, A. B.; Hins, A. G.; Burt, W. R. & Beatty, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Mass Transfer of Single, Solid Uranium Spheres to Flowing Molten Cadmium in Laminar and Turbulent Flow

Description: From Summary and Abstract: "In this study, a 1/2-inch diameter uranium sphere was used and molten cadmium was pumped past the test spheres at different flow rates. Mass transfer coefficients were determined from weight losses of the test spheres."
Date: September 1965
Creator: Traylor, E. Dean
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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Automated Approach to Quantitative Error Analysis in Neutron Transport Calculations

Description: A method is described how a quantitative measure for the robustness of a given transport theory code for coarse network calculations can be obtained. A code, that performs this task automatically and at only nominal cost, is described and has been implemented for slab geometry. This code generates also user oriented benchmark problems which exhibit the analytic behavior at interfaces.
Date: September 1976
Creator: Bareiss, Erwin H. & Derstine, Keith L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Examination of the SCEPTRE and CSMP Programs for Solving the Point-Kinetics Equations with Feedback

Description: Two modeling programs, SCEPTRE and CSMP, are used to solve the point-kinetics equations - - seven coupled nonlinear differential equations - - with a linear-feedback function. The constants used are appropriate for EBR-II; therefore the computational accuracy may be tested against the experimental rod drops. Run-time, versatility, programming ease, and accuracy are criteria used to evaluate the two programs. SCEPTRE is found to be more efficient in run time and CSMP more versatile. The ease of … more
Date: September 1976
Creator: Walkowski, P. D. & Peterson, B. R. (Bruce R.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Microstructural Effects and Signal-Enhancement Techniques in Ultrasonic Examination of Stainless Steel

Description: Ultrasonic inspection of large-grain stainless steel and stainless steel welds is difficult, and the results obtained are not easily interpreted. In the present study, the effects of stainless steel microstructure on ultrasonic test results are described, and several signal-processing techniques for enhancing ultrasonic flaw signals are discussed.
Date: September 1976
Creator: Kupperman, D. S. & Reimann, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Physics Studies in the GCFR Phase-II Critical Assembly

Description: The reactor physics studies performed in the gas cooled fast reactor (GCFR) mockup on ZPR-9 are covered. This critical assembly, designated Phase II in the GCFR program, had a single zone PuO₂-UO₂ core composition and UO₂ radial and axial blankets. The assembly was built both with and without radial and axial stainless steel reflectors. The program included the following measurements: small-sample reactivity worths of reactor constituent materials (including helium); ²³⁸U Doppler effect; uraniu… more
Date: September 1976
Creator: Pond, Robert B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Technology Utilization/Commercialization Activities at Argonne National Laboratory

Description: Technology utilization/commercialization is the process of applying technology to satisfy a preexisting need. The present report examines the organizational relationships involved, the controlling factors, and the role of the technology agent. Included is a brief assessment of the technology commercialization activities currently under way as part of specific research and development projects at Argonne National Laboratory. In addition to the usual supporting references, an appendix is devoted … more
Date: September 1976
Creator: Venard, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alternative Fuel Cycle Options : Performance Characteristics and Impact on Nuclear Power Growth Potential

Description: The fuel utilization characteristics for LWR, SSCR, CANDU and LMFBR reactor concepts are quantified for various fuel cycle options, including once-through cycles, thorium cycles, and denatured cycles. The implications of various alternative reactor deployment strategies on the long-term nuclear power growth potential are then quantified in terms of the maximum nuclear capacity that can be achieved and the growth pattern over time, subject to the constraint of a fixed uranium-resource base. The … more
Date: September 1977
Creator: Chang, Y. I.; Till, C. E.; Rudolph, R. R.; Deen, J. R. & King, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Bubble Dynamics in a Superheated Liquid

Description: This report presents an extensive literature survey on bubble dynamics. Growth of a single spherical bubble moving in a uniformly superheated liquid is considered. Equations of motion and energy are presented in the forms that take into consideration the interaction between the motion and the growth. The fourth-order Runge-Kutta method is used to obtain a simultaneous solution of equations of motion and growth rate, and the solution is compared with available experimental results. Results for l… more
Date: September 1977
Creator: Sha, William T. & Shah, V. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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