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Behavior of Transistors in a Magnetic Field

Description: Experiments are described which show that magnetic fields can exert a controlling influence on the operating characteristics of point contact transistors. The effect is especially evident when the transistor is operated in its negative resistance region. The frequency of an oscillator can be varied, or a switch made to trigger by applying a magnetic field to the transistor. Some applications of the principle are suggested; many more are evident.
Date: August 11, 1954
Creator: Sander, Howard H.
Item Type: Refine your search to only Report
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Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960

Description: A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date: January 11, 1961
Creator: Sadowski, G. S.
Item Type: Refine your search to only Report
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Design Study of a Pebble-Bed Reactor Power Plant

Description: Sanderson & Porter have carried out a series of studies over the last four years which indicate that the pebble-bed reactor way be an attractive way to obtain low-cost power. At the request of the Atomic Energy Commission, two design studies have been carried out on this concept at the Oak Ridge National Laboratory. The first of these a preliminary design of a 10-Mw(t) reactor experiment, the PRRE, was initiated September 10, and a report on the study was issued November 1960. The second phase … more
Date: May 11, 1961
Creator: Fraas, A. P.; Carlsmith, R. S.; Corum, J. M. & Foster, J.
Item Type: Refine your search to only Report
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Local Reactivity "Worth" in the HRT

Description: The effect of adding small quantities of fuel or poison to the HRT has been estimated using perturbation theory. The results have been reduced to a single relation and a set of graphs which make the estimation of added reactivity relatively simple. The perturbation theory results are compared with multigroup results and reasonable agreement is demonstrated; however, there is some question concerning the prompt neutron lifetime.
Date: October 11, 1960
Creator: Jaye, S. & Vondy, D. R.
Item Type: Refine your search to only Report
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Dry Maintenance Facility for the HRT

Description: A portable shield has been designed, developed, fabricated and shop tested to provide the HRT with a facility for direct dry maintenance operations. It provides temporary replacement for any one of the lower roof plugs and should permit many operations to be performed without flooding the reactor cell with water.
Date: October 11, 1960
Creator: Holz, P. P.
Item Type: Refine your search to only Report
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Two-Liquid-Phase Temperature Limits for the Homogeneous Reactor Fuel Solution and its Concentrates; Comments on Solid-Liquid Equilibria.

Description: Temperatures are given at which two liquid phases form in a synthetic homogeneous reactor fuel solution and its concentrates. The data show a two-liquid-phase boundary temperature of 332°C for the Particular HRT Fuel composition and a flat minimum temperature of 305°C for the initial solution concentrated between 300 and 329°C are presented to indicate solution stability in this temperature region. Some related comments on current HRT operations are given.
Date: August 11, 1959
Creator: Marshall, W. L.; Gill, J. S. & Moore, R. E.
Item Type: Refine your search to only Report
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The Effects of Temperature and Composition on the Mercury Vapor Pressure in the Uranium-Mercury System

Description: The use of mercury as a solvent in the recovery of uranium from spent fuels is of the interest at Oak Ridge National Laboratory. The vapor pressure of mercury is lowered by increased concentration of uranium. By dew-point measurements, the vapor pressure at 175°C was found to very between 2 and 8mm of mercury, and at 375°C, between 300 and 1100 mm of mercury, depending upon composition as described below. Plots of the log of mercury vapor pressure vs. the reciprocal of absolute temperature gave… more
Date: June 11, 1959
Creator: Forsberg, H. C.
Item Type: Refine your search to only Report
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Removal of Fission Product Gases from reactor Off-Gas Streams by Adsorption (Presented at American Nuclear Society Meeting, Detroit, Michigan, December 10, 1958)

Description: In the operation of nuclear reactors, nuclear fuel reprocessing plants and in-pile experiments, special provision must be made for disposal of gaseous fission products to prevents contamination of the atmosphere to an unacceptable degree. A disposal process is described in which the noble gas fission products, krypton and xenon, are delayed relative to the sweep gas by physical adsorption as they pass through an adsorbent such as activated charcoal. A theoretical plate analysis, and has been ve… more
Date: June 11, 1959
Creator: Browning, W. E.; Adams, R. E. & Ackley, R. D.
Item Type: Refine your search to only Report
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A Comparison of Elementary Criticality Calculations with Experimental Results

Description: Several experiments have been performed at ORNL with light water solutions of uranyl nitrate (highly enriched in either U^233 or U^235) in an essentially bare sphere 27 inches in diameter. This report presents the results of several calculations with elementary bare reactor theory and a discussion of the observed discrepancies between the calculated and experimental results. If the observed critical concentration is used in the calculations, the calculated effective multiplication constant is l… more
Date: June 11, 1959
Creator: Nestor, C. W., Jr
Item Type: Refine your search to only Report
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Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-1 and E-2

Description: After two batches (~ 340 kg) of fluoride salt from the ARE were reprocessed, pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF6) escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF6 product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The product met both chemical purity and activity specifications for … more
Date: May 11, 1959
Creator: Culler, F. L.
Item Type: Refine your search to only Report
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High-Frequency Titration as Applied to the Determination of Thorium, Uranium, Sulfate, and Free Acid. Parts I Through V.

Description: The technique of high-frequency titrimetry has been applied to the determination of thorium, uranium, sulfate, and free acid. In Part I of this report, the reproducibility of the method for the titration of standard solutions which contained 50mg of thorium in the absence of interferences is established. The coefficient of variation of the method, under these conditions, was found to be less than one per cent. In Part II, the effect of uranium on the high-frequency titration of thorium, as well… more
Date: May 11, 1959
Creator: Menis, Oscar
Item Type: Refine your search to only Report
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Recrystallized Texture of Alpha Uranium

Description: Uranium was plastically deformed 90% at room temperature by unidirectional rolling to a foil 0.002-inches thick. Specimens were recrystallized in the alpha region and several pole figures obtained from 0 to 40 degrees. From these, the preferred orientation was found to be in a spread of idealized (11) [010] about [010].
Date: January 11, 1955
Creator: Seymour, W. & Duffey, J.
Item Type: Refine your search to only Report
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Gas Plated Coatings on Metals and Alloys : Progress Report No. 1

Description: The object of this project is to conduct studies on the coating of metals and alloys by the gas plating process. Coatings to be studied consist of chromium on copper; alloys of nickel chromium on copper; molybdenum on stainless steel and Inconel; chromium on stainless steel and Inconel; and tungsten and molybdenum and their carbides on stainless steel and Inconel.
Date: March 11, 1953
Creator: Nack, Herman & Whitacre, John R.
Item Type: Refine your search to only Report
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Grüneisen's Law and the Fusion Curve at High Pressure

Description: A method to determine the correction to Grüneisen's law corresponding to the effect of the electrons at high pressure. It is assumed that the lattice contribution to the pressure is small and that the equation of state of the solid can be approximated by results of the statistical Thomas-Fermi atom model for the electron pressure.
Date: April 11, 1955
Creator: Gilvarry, J. J. (John James), 1917-
Item Type: Refine your search to only Report
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A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia

Description: The continuous dissolution of 304 stainless steel and stainless steel-UO2 alloy in dilute aqua regia was studied with subsequent stripping of the dissolver product to remove chloride ion. The process has the advantage of producing, by means of a simple head end treatment, a solvent extract feed in a conventional nitric acid medium so that existing solvent extraction processes, materials of construction and waste disposal methods can be used. The purposes of this study were to investigate the va… more
Date: October 11, 1957
Creator: Kitts, F. G. & Perona, J. J.
Item Type: Refine your search to only Report
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Experiments on the Release of Fission Products from Molten Reactor Fuels

Description: Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types, have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of rare gases, iodine, bromine, cesium, and rubidium. In the presence of air or water… more
Date: March 11, 1958
Creator: Parker, George W. & Creek, George E.
Item Type: Refine your search to only Report
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The Reaction of Zirconium with Uranium Dioxide

Description: An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date: June 11, 1957
Creator: Robinson, M. T.
Item Type: Refine your search to only Report
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Cross Sections for OCUSOL-A Program

Description: The OCUSOL-A program (ORNL-CF-57-6-4) for Univac is a modification of the Eyewash (ORNL-1925) multi-group, multi-region reactor code. The group=energy-lethargy-temperature relationship are given in Table A. The element code numbers are given in Table B. The cross sections now on the sigma-tape are given in tables in the Appendix numbered with the element code number. This technical report explains the bases for choosing the cross sections.
Date: June 11, 1957
Creator: Roberts, J. T. & Alexander, L. G.
Item Type: Refine your search to only Report
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A Brief Review of thermal Gradient Mass Transfer in Sodium and NaK Systems

Description: The fact that material transport does occur under conditions of finite temperature difference in a flowing molten metal system was established. The rate mass transfer was thought to be either diffusion limited or solution rate limited. It is believed that the mass transfer of structural materials in Na or NaK systems is solution rate limited. The limiting process has not been qualitatively or quantitatively confirmed for the Inconel-Na or Inconel-NaK system. Increasing the maximum system wall t… more
Date: February 11, 1957
Creator: DeVan, J. H. & West, J. B.
Item Type: Refine your search to only Report
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Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores

Description: A series of two-group calculations has been made on the Oracle for the purpose of obtaining critical-mass and flux distribution data for various ORR core configurations. The 3G3R code of Bate, Einstein, and Kinney was used, together with the RSP code developed by Nelson. This made it possible to obtain results for the three-dimensional case. The results, which are presented graphically, are intended to serve as a guide for the design of experiments until such time as actual measurements are ava… more
Date: March 11, 1958
Creator: Binford, F. T.
Item Type: Refine your search to only Report
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Curve Plotting Routine for the Oracle

Description: A general program has been written to plot curves on the Oracle curve plotter. A description of the code and complete instructions for preparation of input tapes and operation of the code are given. The code tape is available from the Mathematics Panel or from the author.
Date: April 11, 1957
Creator: Lietzke, M. P.
Item Type: Refine your search to only Report
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Semipermanent Freeze Plug Tests for HRT-CP

Description: Five uninsulated semipermanent freeze coils, series connected, can be frozen when submerged in 70 F water with a Freon-11 flow rate of 1.85 gpm at an inlet temperature of -40 F. The refrigeration unit of the HRT-CP is capable of delivering >3 gpm to a similar semipermanent freeze coil system located in Cell C. Therefore the number of F-11 risers required in Cell C of the HRT-CP can be minimized by series connecting this many semipermanent freeze coils where required.
Date: March 11, 1957
Creator: Winget, R. H.
Item Type: Refine your search to only Report
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Control System for HRT Cooling Water

Description: The circuits described herein and shown functionally in Fig. 1 are to be added to the HRT control circuit to provide control and protection for the revised HRT cooling water system. The circuitry will provide protection against excess pressure in the demineralized cooling water loop and cooling water activity, will initiate action to insure containment of activity in event of an explosion and will provide emergency cooling water from the tower basin when required.
Date: February 11, 1957
Creator: Moore, R. L.
Item Type: Refine your search to only Report
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Radioactive Waste Disposal and Miscellaneous Work : Annual Report for Calendar Year 1956

Description: An annual report is given on the operation and costs of waste-disposal facilities at ORNL laboratories and operating buildings in the Bethel Valley area. The operations of the hot-chemical and metal-waste systems, the process-waste system, and the radioactive-gas-disposal system which utilized the 250-ft stack located in the Radioisotope area are discussed. The miscellaneous operations which include the SS (source and special nuclear) material control, SS material recovery, off-shift service fo… more
Date: September 11, 1957
Creator: Seagren, H. E. & Witkowski, E. J.
Item Type: Refine your search to only Report
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