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Standard X-ray Diffraction Powder Patterns: Section 18. Data for 58 Substances
No Description Available.
Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements
Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs.
Hazard Summary Report on the Experimental Boiling Water Reactor (EBWR)
Report discussing possible hazards and preliminary safeguards for a 20-megawatt Experimental Boiling Water Reactor (EBWR) power plant
Design of the Argonne Low Power Reactor (ALPR)
Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly from the reactor to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over-all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading." (p. 15)
Experimental Breeder Reactor-II (EBR-II) Shield Design
No Description Available.
Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors
Report concerning the study of the two-phase flow through the cooling channels of a natural-circulation boiling water nuclear reactor. "One-dimensional conservation equations describing the flow through each channel are written in the linearized perturbed form, and Laplace transformation in time is performed." (p. 5)
The Control of Condensation Heat Transfer Rates Using an Electromagnetic Field
Report issued by the Argonne National Laboratory over "the use of an electromagnetic field to control the laminar film condensation of a vapor whose liquid is electrically conducting" (p. 7). This report includes tables, and illustrations.
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle
Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).
Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow
No Description Available.
The Facility 350 Helium-Atmosphere System
Report describing the helium atmosphere system in the Argonne National Laboratory's Facility 350. The atmosphere's ability to remove moisture, oxygen, and other impurities, how the atmosphere is purified, and experimental data regarding the use of activated carbon to absorb oxygen from helium are discussed.
Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)
Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR-II and the Fuel Cycle Facility, which is in an adjacent building." (p. 13)
Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat
Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory.
Design Summary Report on the Juggernaut Reactor
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.
Design and Hazards Summary Report Boiling Reactor Experiment V (BORAX V)
Report describing the design and usage of the BORAX V nuclear reactor, its surrounding facility, systems, experimental programs, and possible hazards.
Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III
Report documenting the fast zero power reactor experiment (ZPRG-III). This includes a description of the experiment and the reactor, hazards, and accidents.
Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam
Report concerning the corrosion of several ternary zirconium alloys using distilled water at 350 degrees Celsius or ssteam heated to 540 degrees Celsius and 600 psi.
EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations
Report containing zero power (<1 kw) Dry Critical Experiments that were "to be conducted in the EBR-II Reactor prior to filling the Primary System with sodium coolant" (p. 7.) The two primary objectives of these experiments were to determine how well the system performed without sodium coolant and to "determine and/or verify certain operational data to permit modification or improvement of the system (neutron shield, instrumentation, etc.) prior to the introduction of sodium into the system" (p. 7.)
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters
Report estimating the merits of a variety of nuclear reactor concepts for use as external superheaters to be added on to a steam-producing nuclear power plant.
Hazards Summary Report on the Oxide Critical Experiments
Report describing a zero-power reactor facility (ZPR-VII), its systems, and associated hazards.
The Fabrication of Certain Jacketed Uranium Helices
Report describing the fabrication of Doppler Helices, which were 1/8 inch diameter x 12 foot long uranium core completely enclosed within a thin metal jacket and wound into a spring or helix shape.
Boiling Water Reactor Technology Status of the Art Report: Volume 1., Heat Transfer and Hydraulics
Report discussing state of the art design and operation of heat transfer and hydraulics equipment and technology in boiling water reactor power plants.
A General Method for Comparing Thermal Performance of Fuel Element Geometries and Coolants for Non-Boiling Reactors
Report containing a method "for comparing the influence of various fuel element geometries on rector core shape or different specifications of thermal performance"(p. 7).
The Electrical Design of the EBR-II
Report that "summarizes the electrical design of the Experimental Breeder Reactor II Facility (EBR-II). It attempts to gather together and present in reasonable detail the essential features and workings of the completed design, and to present a concise overall view of the system" (p. 11).
A Computer Program for the Kinetic Treatment of Radiation-Induced Simultaneous Chemical Reactions
No Description Available.
Bending of Circular Plates Under A Variable Symmetrical Load
Report containing "analyses of thin, flat, circular plates subject to bending" (p. 7) using various equations for use as equipment for the Argonne National Laboratory Zero Gradient Synchrotron.
Frequency-Response Analysis of Steam Voids to Sinusoidal Power Modulation in a Thin-Walled Boiling Water Coolant Channel
Report regarding a study with the primary objective of acquiring "experimental data on power-to-void transfer functions for a single rectangular flow channel at elevated pressures" (p. 9).
Bending of Circular Plates Under A Uniform Load on a Concentric Circle
Report containing "analyses of thin, flat, circular plates subject to bending" (p. 7) using various equations for use as equipment for the Argonne National Laboratory Zero Gradient Synchrotron.
An Investigation of Instabilities Encountered During Heat Transfer to a Supercritical Fluid
Report concerning "the unstable behavior of a heat-transfer loop operating at a super-critical pressure (p. 7)" within a nuclear reactor.
Safety Analysis Report, Argonne Fast Critical Facility (ZPR-VI)
Report by the Argonne National Laboratory evaluating the Argonne Fast Critical Facility, ZPR-VI, under construction during the course of the study. The study addresses various functionalities and safety features of the facility.
Design and Performance Characteristics of Magnetic Jack-Type Control Rod Drive
Report concerning the design of the magnetic jack, which is a "hermetically sealed, step-motion linear motor which satisfies the need for a reliable, low-cost, nuclear reactor control rod drive." (p. 5)
Hazards Evaluation Report Associated With the Operation of EBWR at 100 MW
No Description Available.
Breeding-Gain Specimens for EBR-I Core IV
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.
A Lunar Power Plant
Report issued by the Argonne National Laboratory over studies conducted on designs for a lunar power plant. As stated in the abstract, "a concept of a nuclear power plant to be assembled on earth and operated on the moon in presented" (p. 9). This report includes tables, illustrations, and photographs.
Fast Fuel Test Reactor - FFTR Conceptual Design Study
Report describing the design of a Fast Fuel Test Reactor (FFTR), analyses of of the reactor's operations, related costs, and possible future projects.
Gas-Cooled Reactors in the USA: A Survey and Recommendation
Report that provides "an understanding of the status of gas-cooled reactors as used for unclassified applications" and determining "phases of advanced research and development needed in the field and from these to recommend a program for high-temperature, gas-cooled reactors" (p. 5).
Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1962 - December 1, 1962
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1959 - March 1, 1960
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Applications of Waveguide and Circuit Theory to the Development of Accurate Microwave Measurement Methods and Standards
Report issued by the Bureau of Standards over "the basic theory and analytical methods used in the development of accurate microwave measurement methods and standards" (p. x). These methods are presented and discussed. This report includes tables, illustrations, and photographs.
Conductive Flooring for Hospital Operating Rooms
Report issued by the Bureau of Standards over studies on the importance of conductive flooring in hospitals. Types of conductive flooring are compared, and tested. The methods and results are presented, and discussed. This report includes tables, illustrations, and photographs.
Colorimetry
No Description Available.
Bibliography and Index on Vacuum and Low Pressure Measurement, January 1960 to December 1965
No Description Available.
Acceleration Due to Gravity at the National Bureau of Standards
No Description Available.
Capacities of Stacks in Sanitary Drainage Systems for Buildings
No Description Available.
The 1958 He4 Scale of Temperatures: Part 1. Introduction, Part 2. Tables for the 1958 Temperature Scale
Report containing information regarding He4 vapor pressure measurement as of 1958, the recent history of the vapor pressure temperature scale, and a series of tables containing these measurements.
Acid-Base Behavior in Aprotic Organica Solvents
No Description Available.
Standard X-ray Diffraction Powder Patterns: Section 6. Data for 60 Substances
No Description Available.
Standard X-ray Diffraction Powder Patterns: Section 5. Data for 80 Substances
No Description Available.
Standard X-ray Diffraction Powder Patterns: Section 9. Data for 63 Substances
No Description Available.
Standard X-ray Diffraction Powder Patterns: Section 12. Data for 57 Substances
No Description Available.
Standard X-ray Diffraction Powder Patterns: Section 8. Data for 81 Substances
No Description Available.