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1A Heat Exchanger Leak Test. Core I, Seed 2. Test Evaluation. Section 2

Description: An investigation was conducted to determine which tubes of the 1A loop heat exchanger are leaking. Air pressure and probing tests are inconclusive and cannot be used to verify chemical sampling. (J.R.D.)
Date: July 24, 1961
Partner: UNT Libraries Government Documents Department
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After Shutdown Cooling Requirements in the HFIR

Description: In order to insure against damage to the reactor in the event of a power failure, it is recommended that emergency forced circulation be provided for a period of about one hour after shutdown. After about one day's decay time, natural circulation cooling on the outside surface of a single fuel annulus should provide sufficient cooling to prevent meltdown. Maximum possible heat up rates at shorter decay times are indicated.
Date: July 20, 1961
Creator: Winters, C. E.
Partner: UNT Libraries Government Documents Department
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Applied Health Physics Annual Report for 1960

Description: Although there were the ususl fluctuations in background at certain of the monitoring stations, the contamination levels recorded do not differ significantly from those of the previous year except that there appears to be a slight trend downward. Data are tabulated. This downward trend can be attributed to a curtailment of operations at the Laboratory, the gradual implementation of the containment program, and a curtailment in world-wide weapons testing. Tall-out data are included. Two personne… more
Date: July 27, 1961
Partner: UNT Libraries Government Documents Department
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Aqueous Processes for Dissolution of Uranium-Molybdenum Alloy Reactor Fuel Elements

Description: Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric acid--ferric nitrate, and nitric acid-- phosphoric acid solutions were studied on a laboratory scale. Flowsheets based on the results propose dissolution of alloys containing 3% molybdenum in boiling 6 M HNO/ sub 3/ to yield stsble solutions that are 0.6 M in uranium and 3 to 4 M in nitric acid. The uranium can then be easily decontaminated and recovered in a conventional Purex-type tributyl phosph… more
Date: July 14, 1961
Creator: Ferris, L. M.
Partner: UNT Libraries Government Documents Department
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Barytes Concrete for Radiation Shielding: Mix Criteria and Attenuation Characteristics

Description: Concrete mix design criteria, based on existing theories of proportioning and specifically oriented toward the solution of radiation shielding problems, were developed. Effects of aggregate gradation, cement-to- aggregate ratio, and water content were examined. A barytes concrete, designed according to these criteria, was thoroughly investigated in the Lid Tank Shielding Facility. Relative effectivenesses of dry aggregates, aggregates plus cement, and cured concrete were compared through therma… more
Date: July 25, 1961
Creator: Grantham, W.J. Jr.
Partner: UNT Libraries Government Documents Department
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Calculation of the"Negative Mass" Instability for DCX-1

Description: The threshold for an instability by which space charge accumulates in a ring of ions circulating in a magnetic field with negative radial gradient is calculated for DCX-1. With present low densities, the energy spread necessary to quench the instability, a dew tens of Kev, is of the order of the observed energy spread.
Date: July 3, 1961
Creator: Fowler, T. Kenneth
Partner: UNT Libraries Government Documents Department
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Capacities of Stacks in Sanitary Drainage Systems for Buildings

Description: "Some of the important results obtained in investigations of capacities of plumbing stacks in test systems at the National Bureau of Standards and elsewhere are discussed. Data are shown from experiments on the flow of water and air in such systems, and analyses of certain flow phenomena are given. Methods are shown for applying the results of research in hydraulics and pneumatics to the preparation of loading tables (for drainage and vent stacks) suitable for use in plumbing codes" (p. 1).
Date: July 3, 1961
Creator: Wyly, Robert S. & Eaton, Herbert N.
Partner: UNT Libraries Government Documents Department
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CHARACTERIZATION OF UO$sup 2$ POWDERS. Progress Report No. 8, May and June 1961

Description: Correlation of a number of physical and chemical properties of 12 different UO/sub 2/ powders was continued. The UO/sub 2/ powders were studied by means of infrared absorption measurements, oxidation temperatures as determined by hot stage microscopy techniques, and B. E. T. surface area measurements. Additional pellets were prepared to study ceramic performance. (M.C.G.)
Date: July 19, 1961
Creator: Carpenter, J.F.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: June 1961

Description: This report, for June 1961 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: July 21, 1961
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Chemical Reactions In Crossed Molecular Beams

Description: Even in its present primitive stage the molecular beam method promises to open up many opportunities for detailed studies of reactive collisions. The early results described here have revealed several features inaccessible to the traditional methods of kinetics. We hope this program of beam studies will ultimately provide the basis for constructing a theory of the molecular mechanics of reactions. By borrowing what are now everyday techniques in nuclear physics (modulation of the beams; mass an… more
Date: July 1961
Creator: Herschbach, Dudley R.
Partner: UNT Libraries Government Documents Department
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Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Description: Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: July 28, 1961
Creator: Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
Partner: UNT Libraries Government Documents Department
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THE CORROSION OF ALUMINUM ALLOYS IN THE OAK RIDGE RESEARCH REACTOR

Description: A corrosion testing program designed to estimate the potential service life of aluminum alloys used in the construction of the Oak Ridge Research Reactor (ORR) cooling systems has been in progress for over two years. The five alloys (1100, 3003, 5052, 5154, and 6061) used to the greatest extent in the reactor exhibited continuously decreasing corrosion rates since the first 500-hr inspection. Samples exposed in the core-cooling loop have shown a decrease in corrosion rate from a 2.6 mpy maximum… more
Date: July 1, 1961
Creator: Neumann, P.D.
Partner: UNT Libraries Government Documents Department
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Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam

Description: The alloying of zirconium to improve corrosion resistance has an empirical basis, and satisfactory explanations for the alloying effects are not available. A theory of compensating valencies in the corrosion oxide is proposed, in which cations of lower and higher valence than zirconium (+4) are present in ratios such that electrostatic neutrality is ensured. An example is an alloy containing equimolar amounts of scandium (+3) and niobium (+5). A number of zirconium alloys were prepared in which… more
Date: July 1, 1961
Creator: Misch, R.D. & Van Drunen, C.
Partner: UNT Libraries Government Documents Department
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CURRENT STATUS OF THE AC IONIZATION CHAMBER

Description: ABS>The design concept of an a-c ionization chamber and its supporting electronics is described. Several designs are possible and the sensors can be tailored to specific requirements when necessary. Mode of operation, signal voltage development, and switching frequency are discussed. High-sensitivity operation is described. Requirements for high-temperature, power-level operation are outlined. (M.C.G.)
Date: July 1, 1961
Creator: Rusch, G.K.
Partner: UNT Libraries Government Documents Department
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Current-Switching Circuitry

Description: This paper discusses a group of high-speed switching circuits using the basic current-switching mode of operation. The first part of the paper presents a dynamic analysis of the basic current-switching mode and the second part is the dynamic and steady-state analysis of a current-switching flip-flop.
Date: July 17, 1961
Creator: Salvador, Jack Gilbert & Pederson, D. O.
Partner: UNT Libraries Government Documents Department
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A DESCRIPTION OF INTEGRAL PHYSICS DATA FOR FAST REACTOR DESIGN

Description: Integral physics data for fast reactor design are discussed. The measurements needed include those of critical mass, shape factor, detector ratios, neutron spectra, material replacement experiments, reflector savings, neutron lifetime, Rossi- alpha , and similar quantities. Topics covered include Pu- and U/sup 233/-fueled systems, highly enriched U/sup 235/ systems in optimum geometry, uranium cores of various enrichments and dilutions, extreme geometry critical experiments, specific reactor sy… more
Date: July 1, 1961
Creator: Loewenstein, W.B. & Meneghetti, D.
Partner: UNT Libraries Government Documents Department
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Design Criteria for Steel in Nuclear Reactors

Description: S>Criteria for stress analysis and structural design with steel for the critical components of nuclear plants are presented. An effort was made to integrate the effects on the strength of steel of the coexisting phenomena, such as mechanical and thermal loads, stress cycling and fatigue, creep and creep rupture, irradiation, and loss of ductility. Extensive use of the plastic region of steel was made for the accommodation of thermal stresses. The concept of cumulative damage in the plastic regi… more
Date: July 1, 1961
Creator: Fistedis, S.H.
Partner: UNT Libraries Government Documents Department
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