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Filling and Emptying System, Cannelton Main Lock, Ohio River, and Generalized Tests of Sidewall Port Systems for 110- by 1200-ft Locks: Hydraulic Model Investigation

Description: Report providing the results of a hydraulic model investigation of the Cannelton Lock proposed for construction on the Ohio River. It includes detailed information about the tests and suggested dimensions and features of the final lock.
Date: February 1966
Creator: Ables, Jackson H., Jr. & Boyd, M. B.
Partner: UNT Libraries Government Documents Department
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Design and Construction of a Unit for Measuring Metal Skin Temperatures

Description: From summary: This report concerns the theoretical evaluation and experimental development of special thermocouples capable of being accurately located at or near the surface of metal structures to permit measurement of temperature distribution through the strictures.
Date: February 1961
Creator: Advanced Technology Laboratories
Partner: UNT Libraries Government Documents Department
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100-C water plant

Description: System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reactor use, 10,000 to 12,000 gpm was demanded by B Area through the 183 BC intertie. The maximum flow that the intertie line could handle, without reducing the filter capacity of the C Area filters, is about 21,000 gpm.
Date: February 20, 1961
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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New K Reactor aluminum HCR: Temperature study

Description: Recent (HCR) Horizonal Control Rod operating problems at the K Reactors, caused primarily by graphite stack distortion, have stimulated several designs of HCR`s capable of operating under adverse conditions. One such design is an aluminum HCR, not completely dissimilar to the present HCR`s, conceived by the Research and Engineering Operation of I.P.D. The successful use of aluminum as a structural material is strongly dependent upon the operating temperature of the aluminum. This study was conducted to determine anticipated operating temperatures of the HCR during reactor operation at the present K Reactor conditions.
Date: February 17, 1964
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Pacific Northwest Laboratory monthly activities report, January 1968

Description: Analysis of Columbia River temperature trends indicates conformity with those previously reported. Despite unusually high average temperatures, the temperatures of the upper and lower extremes continued to converge on the mean. The construction of the John Day Dam is expected to have little temperature effect other than a delay of ten days in the timing of the annual temperature peak. Measurements of radioactivity in 465 children were completed at the third Pasco elementary school on January 12. Whole-body counting at the fourth school began on January 24, following lectures to the staff and 17 classrooms. The whole-body counter was recalibrated for K{sup 40} and Zn{sup 65} in late January. Only small modifications in the calibration factors over those currently employed are expected. Washington State Game Department personnel have supplied sufficient pheasant and quail samples shot near the Columbia River for comparison of radionuclide content between species and collection of these samples has been discontinued. The Department of Game continues to supply ``road-kills`` for radiochemical analysis in exchange for x-ray data on the number of birds which contain shot. A game-bird questionnaire for mailing to a statistical sample of Tri-City hunting license holders was drafted in January.
Date: February 1, 1968
Creator: Albaugh, F. W.
Partner: UNT Libraries Government Documents Department
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Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the research and development program for the United States Atomic Energy Commission sodium Components Design Project.
Date: February 15, 1961
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Shielding Against an 800-Mev Proton Beam

Description: Nucleon-meson cascade calculations were carried out and the dose as a function of depth was obtained for an 800-Mev proton beam incident on a shield. The physical properties used for the shielding medium are only a rough approximation to the properties of any particular medium. Muon, neutron, pion, and proton dose rates and fluxes are listed. (auth)
Date: February 21, 1963
Creator: Alsmiller, R. G., Jr. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Transverse Shielding for a 45-Gev Electron Accelerator. Part Ii

Description: In a previous report nucleon-meson cascade calculations were carried out for several cases of interest in the design of the transverse shield for the proposed 45-Bev linear electron accelerator at Starford University. In this report results are given for several additional cases. Muon, neutron, pion, and proton intensities as function of energy and distance for varying angles are given. Corresponding doses are also included. (D.C.W.)
Date: February 28, 1963
Creator: Alsmiller, R. G., Jr.; Alsmiller, F. S. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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A Fuel Reprocessing Plant for Fast Ceramic Reactors

Description: A study was made of the adaptation of the HAPO anion exchange process to the reprocessing of Fast Ceramic Reactor (FCR) fuel using the Idaho Small Plant Concept. It is shown that the anion exchange flowsheet meets the reprocessing objectives of the FCR case and can be adequately accommodated in the Small Plant Concept. Capacities of up to 1550 Md(e) are feasible in the Small Plant and unit reprocessing costs range from 0.14 to 0.28 mills/kwh depending on the number of reactors to be processed. (auth)
Date: February 1, 1962
Creator: Alter, H. W.
Partner: UNT Libraries Government Documents Department
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Ernest Orlando Lawrence

Description: In his relatively short life of 57 years, Ernest Orlando Lawrence accomplished more than one might believe possible in a life twice as long. The important ingredients of his success were native ingenuity and basic good judgement in science, great stamina, an enthusiastic and outgoing personality, and a sense of integrity that was overwhelming. Many articles on the life and accomplishments of Ernest Lawrence have been published, and George Herbert Childs has written a book-length biography. This biographical memoir, however, has not made use of any sources other than the author's memory of Ernest Lawrence and of things learned from him. A more balanced picture will emerge when Herbert Childs biography is published; this sketch simply shows how Ernest Lawrence looked to one of his many friends.
Date: February 1, 1967
Creator: Alvarez, Luis W.
Partner: UNT Libraries Government Documents Department
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EURIPUS-3 AND DAEDALUS--MONTE CARLO DENSITY CODES FOR THE IBM-704

Description: EURIPUS-3 calculates the one-dimensional spatial density of neutrons slowing-down past a given energy in an infinite homogeneous medium consisting of hydrogen and one other isotope with arbitrary mass and energydependent differential-elastic and absorption cross sections. DAEDALUS determines the corresponding spatial distribution of angular integrals of an arbitrary function times the vector flux density. Spatial moments of all density functions are furnished directly. Although scattering angles are calculated by Monte Carlo, the spatial distributions and, in DAEDALUS, the energy distribution are obtained partly from an analytic treatment which, besides saving tinne, enables the output to be in the form of actual density functions at specified planes and energies, rather than histograms covering finite intervals. At certain steps in the computation of both the spatial and energy distributions, part of the analytic treatment is replaced by Monte Carlo in order either to maximize efficiency and/ or to avoid round-off error. The neutron source may be monoenergetic with either isotropic or monodirectional angular distributions, or else the source may be that from deuterons bombarding deuterons. The volume displaced by a cylindrical tube from an accelerator to the source can be accounted for in the neutron first flight but not thereafter. (auth)
Date: February 1, 1960
Creator: Amster, H. J.; Kuehn, H. G. & Spanier, J.
Partner: UNT Libraries Government Documents Department
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Critical Studies of Uranium-Steel and Uranium-Steel-Sodium Fast Reactor Cores. (ZPR-III Assemblies 32 and 33

Description: S>Critical studies of two fast reactor cores are described: one contains uranium and steel; the other contains uranium, steel, and sodium. Experimental results are given for fission ratio, central and edge reactivity coefficients, fuel bunching, average prompt neutron lifetime, and distributed worth measurements. (auth)
Date: February 1963
Creator: Amundson, P. I.; Gemmell, W.; Long, J. K. & McVean, R. L.
Partner: UNT Libraries Government Documents Department
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STAINLESS STEEL WASTES. III. LABORATORY STUDIES OF THE RATE OF REMOVAL OF STAINLESS STEEL IONS BY MERCURY CATHODE ELECTROLYSIS

Description: ABS> The removal rates of iron, nickel, and chromium from synthetic stainless steel waste solutions during electrolysis over a mercury cathode were studied. The loading capacity of the mercury for the stainless steel metals was estimated on the basis of laboratory experiments to be about two% by weight. The laboratory data indicated that, at an electrode potential of --1.80 voits vs S.C.E., 85 ampere-hours per liter of waste removed essentially all of the stainless steel ions from a sulfuric acid solution containing 0.13M metal ions at 35 deg C. (auth)
Date: February 12, 1962
Creator: Anderson, D. R. & Rhodes, D. W.
Partner: UNT Libraries Government Documents Department
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Plutonium Recycle Critical Facility: Final Safeguards Analysis

Description: Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date: February 1962
Creator: Anderson, J. K. & Winegardner, W. K.
Partner: UNT Libraries Government Documents Department
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