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Eddy Current and Ultrasonic Testing of CP-6 Fuel Elements

Description: The fuel element to be used in the Savannah River reactors is a natural uranium slug 1.00 in. in diameter and 8 in. long, encased in a 2S aluminum can 1.080 in. O.D. having a wall thickness of 0.035 in. The slug is bonded to the can with an aluminum silicon alloy, using the Hanford Al-Si process.
Date: December 1953
Creator: McGonnagle, Warren J. & Doe, W. B.
Item Type: Refine your search to only Report
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Effects of Metal Purity and Heat Treatment on the Corrosion of Uranium in Boiling Water

Description: Corrosion rates of present reactor grade uranium were measured in boiling distilled water and were found to have higher values almost by a factor of two then previously reported corrosion rates of uranium. Mallinckrodt biscuit metal showed corrosion rates in the same medium somewhat lower than reactor grade uranium, and high purity metal prepared at Argonne National Laboratory corroded considerably less rapidly than the biscuit metal.
Date: April 14, 1953
Creator: Draley, Joseph Edward, 1919- & McWhirter, J. W.
Item Type: Refine your search to only Report
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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
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The Electrolytic Refining of Uranium

Description: This technical report describes work done on the electrolytic refining of natural uranium in fused salt baths composed of various eutectics of alkali metal chlorides in which were dissolved UF, or UCl3.
Date: August 2, 1953
Creator: Marzano, Carlo, 1905- & Noland, N. A.
Item Type: Refine your search to only Report
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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
open access

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.
Item Type: Refine your search to only Report
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Engineering Properties of Diphenyl

Description: Report issued by the Argonne National Laboratory discussing engineering properties of diphenyl. As stated in the abstract, "data collected from the literature on the vapor pressure, enthalpy, liquid density, and vapor density of pure diphenyl are presented. A Mollier diagram, a temperature entropy diagram, and data on viscosity of diphenyl as a function of temperature are also presented" (p. 5). This report includes tables, and illustrations.
Date: August 11, 1953
Creator: Anderson, Kermit
Item Type: Refine your search to only Report
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Fabrication and Properties of Extruded Silver-Cadmium Control Rods

Description: The production of cross-type control rods having a span of 4-7/8 in., and an arm thickness of 1/8 in., was studied. Extrusion techniques were developed for producing cross-type control rods from each of two alloys; one containing 75% silver-25% cadmium, and the other containing 67% silver-30% cadmium-3% copper. Fabrication of the extruded crosses into clad control rods for the Mark I naval reactor was attempted. A set of unclad control rods for the Zero Power Reactor was produced. The effect of… more
Date: January 1952
Creator: Dwight, Austin E. (Austin Elbert), 1919-
Item Type: Refine your search to only Report
open access

The Fabrication of a Plutonium Helix for a Doppler Experiment

Description: A helix constructed of plutonium was made to test the Doppler temperature effect in ZPR-III. The helix, 1 inch in diameter and 6-1/4 inches long, contained 240 grams of delta-phase plutonium alloy encapsulated in titanium tubing. Four plutonium rods were extruded, joined together, and pushed into a titanium tube. This tube was swaged tightly over the plutonium rod, and the assembly was wound into a coil. Electrical leads to the coil were made by swaging copper tubing over the ends of the coil. … more
Date: December 1958
Creator: Dunworth, R. J.; Rhude, H. V. & Kelman, L. R.
Item Type: Refine your search to only Report
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The Fabrication of Prototype Fuel Elements for the Experimental Boiling Water Reactor and the Experimental Breeder Reactor

Description: The purpose of this program was to develop techniques and methods for producing fuel elements for the Experimental Boiling Water and Experimental Breeder Reactors. Methods for fabricating large tubes, flat plates, and small pins were investigated. The tube and plates contained U-5 w/o Zr-1.5 w/o Nb alloy and were designed for the EBWR. The pins contained U-2 w/o Zr alloy and were designed for the EBR. Cladding and end seal material of Zircaloy-2 was required for the water-cooled EBWR elements. … more
Date: May 1956
Creator: Sawyer, H. F.; Paynton, W. C.; Loewenstein, P. & Corzine, P.
Item Type: Refine your search to only Report
open access

Factors Which Affect Formation and Deposition of Transport Corrosion Products in High-Temperature Recirculating Water Loops

Description: Deposits of corrosion products form on heat transfer surfaces and in radiation flux zones at temperatures around 500F in stainless steel systems operating with circulating water. The report considers the possible harmful effects of such deposits on heat transfer and fluid flow, as well as factors involved in the origin of these corrosion products and in the mechanisms of deposition. The prevention of deposition by chemical, mechanical, and electrostatic methods is discussed.
Date: December 1953
Creator: Wohlberg, C. & Kleimola, F. W.
Item Type: Refine your search to only Report
open access

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
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Gasification of Chars Produced Under Simulated in situ Processing Conditions Quarterly Report: October-December 1975

Description: This effort is being directed toward support studies for the national endeavor on in situ coal gasification. This task involves the investigation of reaction-controlling variables and product distributions for the gasification of both coals and chars utilizing steam and oxygen. Included in this task is the investigation of the effects of using brackish water as the water supply. The high-pressure char gasification system has been received from the manufacturer and is currently undergoing testin… more
Date: 1976
Creator: Fischer, J.; Lo, R.; Young, J. & Jonke, A. A.
Item Type: Refine your search to only Report
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A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction

Description: Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations.
Date: April 1966
Creator: Koppel, L. B.; Alfredson, P. G.; Anastasia, L. J.; Knudsen, I. E. & Vogel, G. J.
Item Type: Refine your search to only Report
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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
open access

The Half-Life of Pu241

Description: This report describes the first estimation of the beta half-life of Pu241 and was made by determining the beta activity associated with plutonium formed by (d,xn) reactions on U258.
Date: December 1953
Creator: Mech, Joseph & Pyle, Gray
Item Type: Refine your search to only Report
open access

Heat Generation in Irradiated Uranium

Description: Report issued by the Argonne National Laboratory discussing the heat generation of irradiated uranium. Methods of heat production in uranium are presented. This report includes tables, and illustrations.
Date: February 25, 1952
Creator: Untermyer, Samuel & Weills, J. T.
Item Type: Refine your search to only Report
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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
open access

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
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