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A Bench-Scale Natural-Recirculation Dissolver

Description: A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated M… more
Date: January 10, 1962
Creator: Erickson, E. E.
Partner: UNT Libraries Government Documents Department
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Critical Path Scheduling of ETR and MTR Reactor Shutdowns

Description: Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date: January 10, 1962
Creator: Jacobs, R. T. & Myers, L. L.
Partner: UNT Libraries Government Documents Department
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INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II

Description: ABS>A series of neutron multiplication measurements made on sub-critical systems containing enriched uranium and plutonium is presented. These measurements involve both aqueous and metal systems. (auth)
Date: January 10, 1962
Creator: Schuske, C.L.; Bell, C.L.; Bidinger, G.H. & Smith, D.F.
Partner: UNT Libraries Government Documents Department
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Literature Survey on World Isotope and Radiation Technology : First Semi-Annual Report Covering the Period from June 15, 1961 to December 14, 1961

Description: The following report is the first semi-annual report of a literature survey designed to investigate the uses and technology of radioisotopes in the countries of the world from 1955 to the present. This survey includes two phases: 1) involves the direct comparison of radioisotopic work in all fields in various countries as demonstrated at international conferences. 2) involves a more detailed examination and evaluation of the individual fields of interest selected previously (Phase II is also ex… more
Date: January 10, 1962
Creator: Haffner, J. W. & Terrell, C. W.
Partner: UNT Libraries Government Documents Department
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Numerical Analysis of Neutron Resonances

Description: Neutron resonances are analyzed numerically by determining the resonant energies, the total widths, and the neutron widths of the resonances. It was assumed that the total cross section can be represented by the sum of single- level Breit-Wigner formulas, with interference between resonance and potential scattering but no interference between resonances; that the Doppler broadening is represented by a Gaussian function; and that the instrument resolution is represented by a Gaussian function. G… more
Date: January 10, 1962
Creator: Atta, S.E. & Harvey, J.A.
Partner: UNT Libraries Government Documents Department
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Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

Description: A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report, December 1961

Description: The height of transfer units in a 6-in.-ID foam-liquid column for isotopic exchange or stripping of Sr using Sr/sup 89/ tracer were 1.4 to 4.6 in. Denitration of Th(NO/sub 3/)/sub 4/ in an agitated trough to give thoria for dispersion into a sol is reproducible. The loading of UF/sub 6/ on a single layer of 1/8in. right circular cylinders of NaF in the presence of a flowing UF/ sub 6/-N/sub 2/ stream showed strong dependence on gas concentration in the range of 0.58 to 8.0 mole% UF/sub 6/ and a… more
Date: April 10, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Corrosion of thorium and uranium during long-term storage

Description: From introduction: "The over-all objective of the present study was to determine the nature and extent of the present study was to determine the nature and extent of the corrosion of these materials under a variety of such storage conditions and to determine the ability of several potential protective coatings to retard this corrosion."
Date: April 10, 1962
Creator: Stephan, Elmer F.; Miller, P. D. & Fink, Frederick W.
Partner: UNT Libraries Government Documents Department
open access

Equations for Bilateral Heat Transfer to Fluids Flowing in Concentric Annuli

Description: Abstract: "Theoretical equations have been derived for calculating heat transfer coefficients for fluids flowing through concentric annuli for the following two cases: (A) constant and equal heat fluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along annular channel. In the derivations, the conditions of fully-established flow, and independence of physical properties with temperature variation across the fl… more
Date: April 10, 1962
Creator: Dwyer, Orrington Embry, 1912-
Partner: UNT Libraries Government Documents Department
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Neutron Thermalization Measurements Using an Electron Linear Accelerator

Description: Discussions are presented concerning integral experiments primarily on water and graphite systems. A description of experimental facilities is included along with details of die-away experiments, infinite-medium spectrum measurements, spatially dependent spectrum measurements, spectrum measurements for graphite systems, and development of a subcritical assembly program. (J.R.D.)
Date: April 10, 1962
Creator: Beyster, J. R.
Partner: UNT Libraries Government Documents Department
open access

PL-3 Project Quarterly Progress Report, January 1, 1962-March 31, 1962

Description: Progress is reported on phase II in sections on final design, procurement, fabrication, testing, packaging, and crew training. A summary of completed phase I work on concept evaluation and preliminary design is also included. (J.R.D.)
Date: April 10, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
open access

The power output and efficiency of thermionic converters connected in series and parallel circuits--Part I

Description: Optimum and off-optimum performance is experimentally obtained for one of the 10 mil spaced, 7 cm/sup 2/ emitter area, cylindrical geometry thermionic converters to be used in the series and parallel connected thermionic converter experiment. The results are presented as graphs of output voltage vs power input, and power output vs power input. The current is the major parameter in both cases. The data in these forms are used to compute the power output of twin converter circults having unequal … more
Date: April 10, 1962
Creator: Holland, J. W.
Partner: UNT Libraries Government Documents Department
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Removal of radioisotopes from the Columbia River by natural processes

Description: Some radioisotopes are introduced into the Columbia River by return of the water used to cool the Hanford reactors. Trace amounts of both fission product and activation product radioisotopes are present and measurable by sensitive radiochemical methods to allow determination of the self-purification processes occurring as the water moves downstream. By comparing the radioisotope input at given times with the amounts present in the river after traveling downstream, a measure of the self-purifica… more
Date: April 10, 1962
Creator: Nielsen, J. M. & Perkins, R. W.
Partner: UNT Libraries Government Documents Department
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Rocket-Borne IR Scanning Radiometer for High Altitude Radiation Measurements

Description: Report describing a transistorized, scanning, filter radiometer designed for use in an Atlas piggy-back pod. The instrument is designed for moderately narrow-band measurements at 2.7, 3.5, 4.3, 4.7, and 6.3 microns of the irradiance arriving at the radiometer from the earth's atmosphere within a small field of view as a function of height above the true horizon. The measurements will be made while the vehicle is in the altitude range 3 x 100,000 to 10 to the 6th power feet. A fairly complete de… more
Date: April 10, 1962
Creator: Smiley, Vern N.
Partner: UNT Libraries Government Documents Department
open access

Cation Exchange in Acetone-Water-Hydrochloric Acid

Description: Abstract: Distribution coefficients have been measured for the partition of metal ions between cation exchange resin and acetone-water-hydrochloric acid solutions. the differences in distribution coefficients of metal ions are greater in acetone-water media than in aqueous media of the same hydrochloric acid concentration. Using distribution coefficient data, conditions for column separations of mixtures can be selected. Column separations of metal ion mixtures can be effected by eluting wit… more
Date: May 10, 1962
Creator: Fritz, James S. (James Sherwood), 1924- & Rettig, Thomas A.
Partner: UNT Libraries Government Documents Department
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Fuel Element Flow Blockage in the Engineering Test Reactor

Description: On December 12, 196l, the Engineering Test Reactor experienced fuel fission breaks which resulted from obstructions to the flow of cooling water through several fuel elements. A total of six fuel elements had breaks in from one to eight fuel plates. A discussion and description of damage to the fuel is presented. The reactor operating conditions preceding the break are described, including events immediately before the manual scram. Results of investigations conducted after the scram, including… more
Date: May 10, 1962
Creator: Keller, F. R.
Partner: UNT Libraries Government Documents Department
open access

Investigation of Thermalstress-Fatigue Behavior of Stainless Steel. The Effects of Gage Length and Specimen Configuration on Thermal-Stress-Fatigue Test Results

Description: The importance of the experimental method to thermalstress-fatigue test results is clarified. It is shown that a significant increase in apparent fatigue life can be obtained by measuring maximum strain per cycle instead of an average strain. Extrapoiation curves are given to convert the litter into the formed. A varying-cross-section specimen of zero'' gage length is shown to allow measurement of true, maximum strain. (auth)
Date: May 10, 1962
Creator: Horton, K. E.
Partner: UNT Libraries Government Documents Department
open access

PL Final Design Report. Volume 6. Plant Performance Analysis

Description: Data and information are presented concerning analyses of PL-2 transient performance, normal startup and shutdown procedures, and shield design. (J.R.D.)
Date: May 10, 1962
Partner: UNT Libraries Government Documents Department
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REACTIVITY CALIBRATIONS AND FISSION-RATE DISTRIBUTIONS IN AN UNMODERATED, UNREFLECTED URANIUM-MOLYBDENUM ALLOY RESEARCH PROGRAM

Description: Completion of zero-power critical experiments with the ORNL Health Physics Research Reactor is reported. A description is given concerning these experiments which were used to determine the critical size, fission-rate distributions, reactivity calibrations of its movable parts, the temperature coefficient of reactivity, and the reactivity effects of the presence of neutron- reflecting materials adjacent to the reactor. (J.R.D.)
Date: May 10, 1962
Creator: Mihalczo, J.T.
Partner: UNT Libraries Government Documents Department
open access

Super-Prompt-Critical Behavior of an Unmoderated Unreflected Uranium- Molybdenum Alloy Assembly

Description: The time-dependent behavior was investigated of the neutron population in an unreflected unmoderated cylindrical assembly of 90 wt.% U (93.2 wt.% U/sup 235/), 10 wt.% Mo alloy following rapid establishment of a super-prompt critical c ondition with negligible initial neutron population. Reactivity increases up to 11 cents above prompt critical resulted in bursts yielding as many as 1.8 x 10/ sup 17/ fissions with reactor periods as short as 16 mu sec and temperature increases as large as 400 de… more
Date: May 10, 1962
Creator: Mihalczo, J.T.
Partner: UNT Libraries Government Documents Department
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