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Automatic Bubble Density Measurement with the Hough-Powell System

Description: The Brookhaven Bubble Chamber Group is developing a Hough-Powell fast analysis system (HPD)1 for bubble chamber photographs. High precision measurements are made with a computer controlled flying spot digitizer. We are currently testing the track selection programs for the system. We have just completed a study of a method for automatic bubble density measurements.
Date: November 18, 1963
Creator: Strand, R. C. & Webre, N.W.
Partner: UNT Libraries Government Documents Department
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Automatic In-Line Monitor for pH, Gamma Activity and Uranium in the Metal Recovery Plant

Description: In connection with the development of in-line analytical equipment for monitoring pH, gamma activity and uranium concentration in process streams, experiments and tests were carried out during the past year and a half in the Metal recovery Plant on a pH monitor for the hydrogen ion concentration in neutralized waste, a continuous gamma activity monitor on the RCU, an automatic photometer for uranium in RAF, and an automatic polarograph for uranium in RAW. This letter is written to present up-to… more
Date: February 18, 1955
Creator: Reas, W. H.; Connally, R. E.; Koyama, K.; Michelson, C. E. & Van Meter, W. P.
Partner: UNT Libraries Government Documents Department
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Chambers Works Process for the Manufacture of Fluorine in East Area Carbon Anode Cells (M.W.38.0)

Description: Historical: This process is based on experimental work done in Jackson Laboratory, Send Works, Blue Products, and East Area. It supersedes the Tentative Chambers Works Process for the Manufacture of Fluorine Using Carbon Anode Units, dated December 2, 1943.
Date: January 18, 1948
Creator: E. I. du Pont de Nemours & Company
Partner: UNT Libraries Government Documents Department
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Concrete Cone Anchor Tests

Description: This study was initiated to determine the minimum safety requirements for safe anchorage of electric pole lines. The objectives were to investigate the suitability of manufactured concrete pole line anchors for use at the Hanford Atomic Products Operation, to design a concrete anchor slug of optimum shape and size for manufacture, to determine by field tests the resistance pullout of the concrete anchor when buried at various depths under the most favorable condition, and to develop a safe desi… more
Date: March 18, 1955
Creator: Buchols, C. S.
Partner: UNT Libraries Government Documents Department
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Control Air Conditions at the Reactor Chamber. Section I. Test Results DL-S-269

Description: The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air i… more
Date: November 18, 1959
Creator: Eckenrode, Gerald E.
Partner: UNT Libraries Government Documents Department
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Core I Control Rod Drive Mechanisms Periodic Tests. Section I. Ninth Performance. Test Results DL-S-148-I, T-550011

Description: The purpose of the test was to determine the operating conditions of the rod drive mechanisms so that operating personnel may be informed concerning malfunctioning mechanisms. The results the this test favorably agree with previous results. The operating characteristics of the rod drive mechanisms checked in this test have not changed appreciably.
Date: November 18, 1959
Creator: Pazuchanics, Nicholas
Partner: UNT Libraries Government Documents Department
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The Corrosion of Miniature Fuel Plates in Simulated Reactor Cooling Water

Description: Technical report issued as one of a series of reports concerned with corrosion studies for the Materials Resting Reactor, created to both determine the effect of various practices for fuel plate fabrication on corrosion resistance and to determine the extent of penetration of the fuel plates by localized corrosion attack. [From Introduction]
Date: December 18, 1950
Creator: English, James L.
Partner: UNT Libraries Government Documents Department
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Criteria for Evaluating Hazards Involved in Proposed Tests On and/or Modifications To the SM-1

Description: Abstract: This technical report elucidates principles of hazards evaluation. The concept of hazards potential is introduced and utilized to show how a reactor system perturbation will influence its nuclear safety. Literature relating to reactor safety is referenced to provide the sources of information required for hazards analysis and show how they influence a hazards evaluation. A checklist of items which should be considered in evaluating a change, test, or modification is presented.
Date: October 18, 1961
Creator: Scoles, J. F.
Partner: UNT Libraries Government Documents Department
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Delta-Phase Zirconium Hydride as a Solid Moderator

Description: Abstract: "In a study of the preparation and properties of delta-phase zirconium hydride it was found that large, sound bodies of the hydride can be prepared by direct combination of the elements if the rate of the reaction is retarded by limiting the supply of available hydrogen. Specimens up to 1-in. diameter were prepared using this technique. Because delta phase zirconium hydride does not readily form eutectics with iron-and nickel-base alloys below 1800 F these materials may be utilized fo… more
Date: December 18, 1957
Creator: Vetrano, James B.
Partner: UNT Libraries Government Documents Department
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Design Criteria for PRP- Critical Facility Project CAH-842

Description: The PRP Critical Facility is an experimental reactor for use in determination of basic nuclear constants of heterogenous reactors recycling plutonium, and exponential and criticality studies at power levels up to 100 watts and neutron fluxes of about 109 nv. Provision is made for changing reactor lattices using irradiated and unirradiated fuel elements with either a light or heavy water moderator.
Date: December 18, 1959
Creator: Nelson, H. K. & O'Neill, G. L.
Partner: UNT Libraries Government Documents Department
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A Design for a Rotary Reactivity Control for a Test Reactor

Description: Tests made on the Oy-Tu reacting assembly at Pajarito indicate that the lateral displacement of two halves of the active material within the assembly can be used as a control mechanism on this type of reacting assembly. This report describes a reacting assembly using a rotary control mechanism based on this principle and indicates the sensitivity of control possible with such a device.
Date: September 18, 1950
Creator: Josephson, V. (Vernal)
Partner: UNT Libraries Government Documents Department
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Development of Techniques for Power Production From Mixed Fission Products

Description: "An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will b… more
Date: February 18, 1961
Creator: Eaton, D.
Partner: UNT Libraries Government Documents Department
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Eddy Transport in Liquid-Metal Heat Transfer

Description: This report seeks to "develop a practical method of evaluating the eddy diffusivity of heat transfer for liquid metals, so that it can be incorporated into the more or less standard theoretical methods to give heat transfer coefficients which are in reasonable agreement with experimental facts"--from introduction.
Date: February 18, 1962
Creator: Dwyer, Orrington Embry, 1912-
Partner: UNT Libraries Government Documents Department
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Effect of Core Corrosion Sample Assembly on HRT Critical Concentration

Description: An estimate has been made of the critical fuel concentration in the HRT, taking into account the effect of the core corrosion sample assembly. The estimate is based on a number of previous calculations of critical concentration in an un-poisoned reactor and one calculation of critical concentration as a function of poison level. The makeup of the first core corrosion sample assembly was used in calculating equivalent neutron poisoning effects. Figure 1 shows the estimated critical concentration… more
Date: July 18, 1957
Creator: Haubenreich, Paul N.
Partner: UNT Libraries Government Documents Department
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The Effect of Fabrication Variables on the Structure and Properties of UO₂-Stainless Steel Dispersion Fuel Plates

Description: From introduction: "This report deals with a part of the research and development studies which preceded the manufacture of fuel elements for the Gas Cooled Reactor Experiment (GCRE)." The studies evaluate the effects of varying the type and size of UO2 particles, stainless steel matrix powders, blending procedures, compacting pressures, sintering times, temperatures and atmospheres, roll-cladding temperatures and reduction rates, total cold reduction, and heat-treating times and temperatures h… more
Date: February 18, 1959
Creator: Paprocki, Stan J.; Keller, Donald L. & Cunningham, G. W.
Partner: UNT Libraries Government Documents Department
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The Effect of Temperature on the Yield Strength of the Polycrystalline Hexagonal Ag-Al Intermetallic Phase

Description: The effect of temperature on the yield strength of the polycrystalline hexagonal Ag-Al intermetallic phase was investigated over the temperature range 77 to 775 K. It was found that the curve for yield stress vs temperature for both polycrystalline Ag-33 at .% Al specimens that were heavily cold worked prior to deformation and those that were recrystallized prior to deformation was parallel to that for prismatic slip in single crystals.
Date: December 18, 1961
Creator: Tanaka, Kichinosuko & Mote, Jim D.
Partner: UNT Libraries Government Documents Department
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Effects of In-Reactor test Loops on PRTR Operation and Program

Description: Recently proposals for justifiable additions to the Plutonium Recycle Test Reactor Complex were presented to the Atomic Energy Commission at their request. In addition to a critical reactivity measuring facility in the fuel element storage basin, the following in-reactor loops were proposed: 1. A high pressure, H2O cooled fuel test loop. 2. A rupture loop to investigate fuel element failures. 3. One or more materials testing loops.
Date: March 18, 1959
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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Electronuclear Research Division Semiannual Progress Report

Description: Nuclear physics research with 22-Mev protons in the 86-in. cyclotron included angular-distribution measurements of neutrons from (p,n) reactions in nine target elements; measurement of the angular distribution of fission fragments from proton-induced fission of U233, U225, U228, Th230, and Th232; measurement of alpha-particle angular distributions from (p,α) reactions a study of the neutron-deficient isotopes of terbium and completion of an extensive program of the measurement of activation cr… more
Date: November 18, 1954
Creator: Livingston, R. S. & Howard, F. T.
Partner: UNT Libraries Government Documents Department
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Electroplating on Zirconium

Description: A two-etchant surface preparation treatment has been found which insures good adhesion between the zirconium and the nickel or copper electroplate. The etching process requires 1 1/2 minutes.
Date: January 18, 1955
Creator: Katayama, Y. B.
Partner: UNT Libraries Government Documents Department
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Engineering Report on the Design of the Pratt & Whitney Aircraft Forced Convection Alkali Metal Vaporization Condensation Heat Transfer Rig

Description: Summary. A test rig has been designed to obtain basic two phase forced convection liquid metal heat transfer and pressure drop data for use in the design of liquid metal boilers. This engineering report includes background of the boiling problem, partial summary of work done by other investigators, the object, scope, engineering, and operations of this test rig, and a summary of reproducibility tests conducted in a water back-up rig.
Date: January 18, 1963
Creator: Bernstein, E.
Partner: UNT Libraries Government Documents Department
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