Technical Report Archive & Image Library (TRAIL) - 99 Matching Results

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Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies

Description: Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date: 1964
Creator: Vogel, G. J.; Carls, E. L. & Mecham, W. J.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report [for] October, November, and December 1955

Description: A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the eliminati… more
Date: June 1965
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Partner: UNT Libraries Government Documents Department
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Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW

Description: From Introduction: "This hazards report covers the basic modifications to the EBWR plant as designed to increase the present operating design rating of 20 Mwt to a new rating of 100 Mwt. it is written as a supplement to ANL-5781 (the original hazards report) and follows the outline of that report for purposes of cross reference."
Date: October 1960
Creator: Wimunc, E. A. & Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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Design of the Argonne Low Power Reactor (ALPR)

Description: 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… more
Date: May 1961
Creator: Hamer, Eberhard E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Partner: UNT Libraries Government Documents Department
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Zero-Power Experiments on the Argonne Low Power Reactor (ALPR)

Description: Report describing the zero-power experiments on the Argonne Low Power Reactor. It is a prototype of a natural-circulation, boiling-water-reactor nuclear power plant designed to supply the electrical power and space heat requirements of a proposed Auxiliary DEW Line radar station.
Date: May 1961
Creator: Shaftman, D. H.
Partner: UNT Libraries Government Documents Department
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Argonaut Automatic Flux Controller Design Report

Description: Report issued by the Argonne National Laboratory over design studies conducted on Argonaut reactors for training and research purposes. As stated in the abstract, "the design presented in the form of a steady-state analysis based upon the small-signal linearization of the reactor kinetics transfer function. The measured controller performance and construction details of the equipment is given" (p. 7). This report includes tables, illustrations, and photographs.
Date: January 1960
Creator: Gerba, A., Jr.
Partner: UNT Libraries Government Documents Department
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Preliminary Design of a Basic Radiation Effects Reactor (BRER)

Description: From Introduction: "Information has been accumulated about the property changes produced, but there are essentially no reliable quantitative data correlating property changes with the magnitude and energy distribution of the neutron fluxes responsible for the changes. The design of the Basic Radiation Effects Reactor (BRER) presented herein stems from the two main requirements: 1. a fairly high-level, high-energy neutron flux with minimal thermal neutron and gamma-ray background is desired; 2. … more
Date: March 1961
Creator: MacFarlane, D. R.; Rohde, R. R.; Toppel, B.; Charak, I. & Unger, H.
Partner: UNT Libraries Government Documents Department
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U.S. Participation in the OEEC Halden Reactor Project May 1959 to September 1960

Description: From Introduction: "This report summarizes the activities of the OEEC Halden Reactor Project, Halden, Norway, during the period of participation in the project by the author, from May 21, 1959 to September 22, 1960. The review is presented here in the interest of completeness of this report, in an effort to provide an impression of the character of research being carried out at Halden."
Date: December 1960
Creator: Fromm, Leonard W., Jr.
Partner: UNT Libraries Government Documents Department
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Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III

Description: Report documenting the fast zero power reactor experiment (ZPRG-III). This includes a description of the experiment and the reactor, hazards, and accidents.
Date: October 1961
Creator: Long, J. K.; McVean, R. L.; Thalgott, F. W. & Novick, M.
Partner: UNT Libraries Government Documents Department
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An Ultrasonic Measurement System for The Precise Determination of the Elastic Moduli of Single Crystals

Description: From Abstract: "The equipment described in this paper is based on the technique developed by McSkimin. Figure 1 shows a block diagram of the system. The oscilloscope presentation with no specimen present appears as shown in Figure 2a. At discrete frequencies, the pattern appears as shown in Figure 2b."
Date: May 1961
Creator: Renken, C. J.
Partner: UNT Libraries Government Documents Department
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A Low Dead-Time Neutron-Counting-System

Description: From Abstract: "This report describes a counting system capable of processing input pulses at an average rate in excess of 3 x 10 to the fifth power counts per second with less than 10 percent counting loss due to instrumental dead time."
Date: January 1961
Creator: Epstein, Robert J. & Thompson, Donald C.
Partner: UNT Libraries Government Documents Department
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EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

Description: 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… more
Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Partner: UNT Libraries Government Documents Department
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Recrystallization in Rolled Uranium Sheet

Description: From Introduction: "To overcome the difficulties another investigation has been carried out wherein the rolling stock was subjected to step reduction and annealing treatments designed to develop a small, uniform grain size prior to the final rolling at room temperature. The results of metallographic, dilatometric, and X-ray diffraction studies of this material are given."
Date: March 1962
Creator: Lloyd, Lowell T. & Mueller, Melvin H.
Partner: UNT Libraries Government Documents Department
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An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

Description: 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.
Date: October 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Partner: UNT Libraries Government Documents Department
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Status Report on the Argonne Advanced Research Reactor

Description: From Introduction: "This is a status report on the interim design and development for an advanced research reactor (AARR) that will produce a maximum thermal neutron flux of 5 x 10 to the fifteenth power neutrons/ (cm2) (sec). As a result, this report also contains sections covering shielding, plant layout, fuel charging, maintenance, and auxiliary facilities."
Date: November 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Partner: UNT Libraries Government Documents Department
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Facility For Photographing in-Pile Meltdown Experiments in TREAT

Description: Report regarding the fabrication of a transparent meltdown facility for the purpose of photographing simulated meltdowns.
Date: January 1962
Creator: Golden, G. H.; Dickerman, C. E. & Robinson, L. E.
Partner: UNT Libraries Government Documents Department
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The Facility 350 Helium-Atmosphere System

Description: 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.
Date: December 1962
Creator: Mayfield, R. M.; Tope, W. G. & Shuck, A. B.
Partner: UNT Libraries Government Documents Department
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Optimization of Efficiency of a Cesium Diode Converter

Description: From Introduction: "The efficiency of the converter is computed with the least possible assumptions. Thermal emissivity and the interelectrode heat-transfer coefficient are varied, and the effect on efficiency is investigated."
Date: March 1962
Creator: Sanathanan, C. K.
Partner: UNT Libraries Government Documents Department
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