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1. K+ Charge Exchange - Search For K+ Charge Exchange

Description: An experiment was designed utilizing a charge-exchange reaction to study the decay and interactions of the neutral K mesons produced. The experiment produced no events that could be interpreted as either the decay or interaction of neutral K mesons. The nature of the experiment and the possible explanations of this unexpected result are presented in this paper.
Date: July 29, 1959
Creator: Birge, Robert W.; Courant, Hans J.; Lanou, Robert E., Jr. & Whitehead, Marian N.
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The Action of Oxygen on Activated Charcoal

Description: The following report provides information conducted with the purpose of ascertaining the effect of oxygen on activated charcoal at approximately one atmosphere by measuring the amount of CO2 formed over a known length of time.
Date: June 29, 1951
Creator: Bigelow, J. E.; Belaga, M. W. & Mulvihill, R. J.
open access

Activation Energy for Fission

Description: Abstract: The experimentally determined exponential dependence of spontaneous fission rate on Z^2/A has been used to derive an expression for the dependence of the fission activation energy on Z^2/A. This expression has been used to calculate the activation energy for slow neutron induced fission and photofission. The correlation with the experimental data on these types of fission seems to be quite good.
Date: August 29, 1952
Creator: Seaborg, Glenn T.
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Airborne Radioactivity Survey of Part of the Navajo Indian Reservation of Utah and Arizona

Description: From introduction: The purpose of an airborne radioactivity survey is to locate ground areas of higher than normal radioactivity which might lead to discovery of uranium mineralization. For this type of survey, gamma-ray detection equipment employing either a geiger counter or a scintillation counter can be mounted in a fixed wing aircraft or a helicopter.
Date: February 29, 1952
Creator: Cummings, Winthrop L.
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All In-Well Permeability Testing Packer

Description: Disposal of liquid radioactive wastes to ground requires knowledge of the area ground-water hydrology. Information is desired on direction and velocity of ground-water flow. Direction of flow can be determined from maps showing contours on the water table surface, such contours being derived from well water elevations. Ground-water velocity is more difficult to ascertain.
Date: September 29, 1959
Creator: Raymond, J. R.
open access

Catalysts for Recombination of Radiolytic Gases Over Thorium Oxide Slurries

Description: Catalysts for use in recombining the gases produced by the radiolytic decomposition of water in thorium oxide slurries under neutron irradiation were investigated in out-of-pile tests using stoichiometric mixtures of hydrogen and oxygen. Most favorable results were obtained with a molybdenum oxide catalyst. Satisfactory rate also were attained with palladium and silver oxides. Copper, nickel, vanadium and chromium compounds were less effective.
Date: January 29, 1957
Creator: Morse, L. E.
open access

The Chemical Processing of Two-Region Aqueous Homogenous Reactors

Description: A promising scheme for the chemical processing of a thorium breeder reactor of the two-region aqueous homogeneous type consists of the following operations: concentration of insoluble fission and corrosion products from the core system into a small volume of fuel solution, combining this slurry with irradiated thorium oxide slurry taken from the blanket, recovery of D2O by evaporation, dissolution of the thorium and uranium in HNO3, and, after a suitable cooling period, recovery of the uranium … more
Date: January 29, 1957
Creator: Ferguson, D. E.
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Chemistry-Separation Processes for Plutonium and Uranium

Description: Attached hereto are copies 1 through 4 of a classified secret report titled "Purex - A Hanford Separations Plant." We are also sending under separate cover a classified confidential report No. HW-36496 titled "Photographs of Purex - A Hanford Separations Plant," which is a counterpart of the above report. These documents are submitted for publication and should be incorporated as a single article.
Date: April 29, 1955
Creator: Mundt, W. J.
open access

Corrosion Status: Sulfex-Thorex (Ni-o-nel) and Darex-Thorex (Titanium) as of June 12, 1959

Description: Either system appears to be fairly satisfactory from a containment standpoint. Current results indicate probable over-all rates of about 0.2mils/mo for titanium vs. 1.5-3.0 mils/mo for Ni-o-nel. Tests are not 100% comparable due to changes made in flowsheet conditions, but have been of sufficient variation and length as to allow good predictions to be made. Both metals show some tendency toward local attack in Thorex solutions. These tendencies are increased by poor welding techniques.
Date: June 29, 1959
Creator: Clark, W. E.
open access

Cracks in HRT Flange Bolts and Ferrules

Description: When it was discovered that two HRT flange bolts of a lot of 16 spares contained serious cracks, a program was launched to (1) determine the cause for the cracking, and (2) find methods for non-destructive testing the remainder of the 672 bolts shipment, a large portion of which had been installed in the HRT. Concurrently, inspection of 8 ferrules removed from an HRT flange revealed hairline cracking in 4 of them. Magnaglo, a magnetic particle inspection method using a fluorescent dye, proved t… more
Date: January 29, 1957
Creator: Hammond, J. P.; Adamson, G. M. & Kegler, T. M., Jr.
open access

Current Beryllium Literature : A Selected Bibliography, January 1958 - August 1959

Description: "This bibliography lists selected articles on beryllium which have appeared in journals received in the library of the Lawrence Radiation Laboratory, Livermore, California and articles, reports, and books which have appeared in the following abstracting services between January, 1958 and August 1959."
Date: September 29, 1959
Creator: Lane, Zanier D.
open access

Darex Pilot Plant Studies

Description: The Atomic Energy Commission has assigned the Hanford Atomic Products Operation the responsibility of providing the technology and facilities for the interim reprocessing of slightly enriched uranium fuels discharged from power and propulsion reactors. The fuel from the various reactors vary greatly in physical dimensions and in the composition of the core and cladding. For the purposes of chemical reprocessing, the fuels may be divided into the three main categories of aluminum, Zircaloy or st… more
Date: October 29, 1959
Creator: Shefcik, J. J.
open access

Decontamination of buildings used for processing alpha emitters

Description: A report regarding many uranium production plants constructed during the existing emergencies and pressures of World War II that were not intended to be permanent instillations. These plants either contractor or government owned, with buildings on the most part belonging to the contactor and a major portion of the processing equipment belonging to the government, became outmoded with the development
Date: April 29, 1954
Creator: Klevin, Paul B.; Harris, W. B. & Blatz, Hanson I.
open access

Determination of Submicron Particle Sized by an Activation Analysis - Centrifugation Method

Description: The feasibility of determining particle sizes in the submicron range by employing an activation analysis - centrifugation method has been demonstrated. It is believed that this method is now applicable to the analysis of thorium oxide for submicron particles. The same techniques are, in most instance, usable in determining particle sized in other sample materials.
Date: January 29, 1957
Creator: Bate, L. C. & Leddicotte, G. W.
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Diffraction Studies of Possible Ordering in α-brass

Description: Recently, there has been some evidence to point to possible ordering in the α-brasses. Masumoto et al. have concluded from their specific heat measurements that there is a possibility of ordering in the α-brasses. In particular they observed an anomaly in the specific heat curves for the α-brasses for the temperature range from 200 to 260°C and explained these results upon the basis of a change in local or short range order in α-brasses at these temperatures. In connection with the study of rad… more
Date: March 29, 1954
Creator: Keating, David, T.
open access

A Doorway Monitor

Description: The purpose of this work was to produce a reliable, inexpensive instrument for the detection of hard beta contamination on the clothing of personnel. Also, the monitoring was required to be accomplished without interrupting the normal activities of the employees.
Date: April 29, 1955
Creator: Campbell, D. A. & Test, L. D.
open access

Effect of Reactor Irradiation on the Thermal Conductivity of Uranium Impregnated Graphite at Elevated Temperatures

Description: "An experiment to determine the effect of reactor irradiation on the thermal conductivity of uranium-impregnated graphite at elevated temperatures as described. The results show a decrease in the thermal conductivity saturating at [approximately] 60 percent at a temperature of 700 degrees C; at [approximately] 50 percent at a temperature of 1000 degrees C; and at [approximately] 25 percent at a temperature of 1300 degrees C. It was found that after irradiation at a given temperature, exposure… more
Date: April 29, 1954
Creator: Durand, Richard E.; Klein, David J. & Nykiel, Harry H.
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Effect of the PRTR High Pressure Loop on Plutonium Recycle Program Objectives

Description: For purposes of an earlier consideration of the effects of in-reactor test loops on PRTR operation and program, the design of the high pressure, H20 cooled fuel test loop was assumed to be similar to that for the high pressure, gas cooled loop. Detailed design criteria for the H20 loop have recently been completed so that this assumption is no longer necessary. Therefore, to insure that the effects of all proposed in-reactor loops are fully evaluated with respect to Plutonium Recycle Program ob… more
Date: October 29, 1959
Creator: Peterson, R. E.
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Electron Loading and High Voltage Sparking of Metals in Vacuum

Description: Statistical methods were employed to measure relative values of electron loading and spark-over voltage for a large number of unoutgassed electrode materials. Test voltages up to 110 KV were employed in vacuum of the order of 10<sup>-7 mm Hg. All metals showed a square root dependence between spark-over voltage and spacing.
Date: June 29, 1953
Creator: Heard, Harry G.
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Evaluation of Glass-Clad Bayonet Heaters

Description: This report describes the results of evaluation tests made on several glass-coated bayonet heaters supplied to Separations Equipment Development by the Pfaudler Company. The glass-coated heaters were found to be resistant to thermal shock, mild mechanical shock, and chemical attack by boiling 60% nitric acid.
Date: July 29, 1955
Creator: Krieg, J. T. & Amos, L. C.
open access

Filling Instructions for the Pratt & Whitney Forced Convection Liquid Metal Inpile Loop Experiment (PW19)

Description: The apparatus and procedures that are to be used to fill the liquid metal system of the Pratt and Whitney Forced Convection Liquid Metal Inpile Loop are described. The liquid metal to be used is a mixture containing 56% Na and 44% K, which is a liquid at room temperature. In order to simplify the filling procedure at the reactor site, two containers, each of which contains exactly enough liquid metal to fill the experiment to the prescribed level, a fill dolly incorporating a purified helium sy… more
Date: April 29, 1959
Creator: Heyl, P. T.
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Final Process Design for Leak Detector System for Special Flanges

Description: The leak detector system consists of one gas pressurized reservoir containing heavy water, a tubing manifold connecting the pressurizer to six separate lines each connected to one of the flanges, tubing lines leading from the second hole on each of three flange pairs (dome and heat exchanger flanges) back into the instrument room, plus required valves and fittings. A schematic diagram of the system in included.
Date: May 29, 1957
Creator: Mason, Edward A. (Edward Allen), 1926-1994
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A Fluoride Fuel In-Pile Loop Experiment

Description: An inconel loop circulating fluoride fuel (62 1/2 make [unintelligible] NaF, 12 1/2 make [unintelligible] ZrF4, 25 make [unintelligible] UF4, 92 [unintelligible] enriched) was operated at 1485°F with a temperature difference of about 35°F in the Low Intensity Test Reactor for 645 hr. For 475 hr of this time the reactor was at full power, and fission power generation in the loop was 2.7 kw, with a max length power density of 0.4 kw/cc. The total volume of fuel was 1290 cc (5.o kg [unintelligible… more
Date: January 29, 1957
Creator: Sisman, Q; Brundage, W. E.; Parkinson, W. W.; Boumann, C. D.; Correll, R. M; Morgen, J. G. et al.
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