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The Path of Carbon in Photosynthesis

Description: Biosynthesis begins with photosynthesis. Green plants and other photosynthetic organisms use the energy of absorbed visible light to make organic compounds from inorganic compounds. These organic compounds are the starting point for all other biosynthetic pathways. The products of photosynthesis provide not only the substrate material but also chemical energy for all subsequent biosynthesis. For example, nonphotosynthetic organisms making fats from sugars would first break down the sugars to sm… more
Date: October 1, 1960
Creator: Bassham, J. A. & Calvin, Melvin
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments With Oxide Fuel Pins

Description: Critical experiments with pin-type oxide fuel elements for the CETR are described. These experiments were conducted to provide data on the infinite medium properties of the lattice inside the canned elements in the various CETR loading zones and to obtain specific information on the fullsize CETR core. Measurements are described and results are interpreted. (J.R.D.)
Date: July 1, 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Evaluation of Mercury Cooled Breeder Reactors

Description: A technical and economic evaluation of a mercury-cooled fast breeder reactor is presented. The objectives of the program were to establish the technical feasibility of a fast breeder reactor cooled with boiling mercury and to evaluate the long-range potential of such a reactor power plant for production of economic power. Details of the conceptual design of a 100-Mw(e) reactor and system are discussed. The power cost from a mercury cooled fast breeder reactor was estimated as 21.4 mills/kwh whi… more
Date: December 14, 1960
Creator: Battles, D.W.
Partner: UNT Libraries Government Documents Department
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Piping changes for increased production at B, D, DR, F, C, and H reactors

Description: This study proposes improvements in the process water piping adjacent to the front and rear faces of these reactors. This report covers the external piping of the reactors from the incoming valve pit to the inlets of the outgoing retention basins.
Date: January 22, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
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Piping Changes for Increased Production at B, D, DR, F, C and H Reactors calculations

Description: On January 22, 1960, HW-63487 Piping Changes for Increased Production at B, D, DR, F, C, and R Reactors, was published. This study investigates the valve pit piping, front and rear face piping,and effluent lines between the 105 Buildings,and the retention basins to determine modifications necessary to increase power levels in the 100-B, D, DR, F, C, and H Areas by increasing either or both temperatures and flows. The study was based on detailed hydraulic and stress calculations of the existing … more
Date: March 24, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
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THE BMI-16 RECIRCULATING GAS LOOP INSTALLED AT THE ETR

Description: A developmental program was conducted to provide and in-pile loop facility for use in evaluating gas-cooledreactor fuel asubassemblies. The program included the design, construction, and installation of a recirculating gas loop which is located in a 6 by 6-in. facility in the aluminum reflector of the ETR. The loop system was designed to recirculate the primary nitrogen coolant at flow rates up to 0.9 lb per sec and pressures up to 200 psia. It will accept fuel subassmeblies up to 36 in. in len… more
Date: March 18, 1960
Creator: Baum, J. V. & Francis, G. A.
Partner: UNT Libraries Government Documents Department
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REACTIONS OF HYDROGEN PEROXIDE AND ION EXCHANGE RESINS

Description: The interaction of dilute aqueous A/sub 2/O/sub 2/ and ion exchange resins was investigated. A mechanism of absorption and decomposition of H/sub 2/ O/sub 2/ on anion exchange resin is proposed. (auth)
Date: April 1, 1960
Creator: Baumann, E. W.
Partner: UNT Libraries Government Documents Department
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SELECTION OF THE PIQUA OMR FUEL ELEMENT

Description: Two types of aluminum-clad uranium alloy fuel elements, a square (parallel flat plate) and a circular (concentric cylindrical shell) were investigated to determine their relative suitability for use in the Piqua Reactor. Nuclear, thermal, and mechanical data are given, and considerations leading to selection of the circular element are presented. Design dimensions are listed and reactor thermal design and operating conditions are given for the proposed element. (auth)
Date: March 15, 1960
Creator: Baumeister, E.B. & Wilde, J.D.
Partner: UNT Libraries Government Documents Department
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LEAKAGE CHARACTERISTICS OF OPENINGS FOR REACTOR HOUSING COMPONENTS

Description: Measurements were made of the air leakage rates through structural components that penetrate semicontainment reactor housing installations. Full- sized test specimens were sealed inside a 10-ft-diameter test sphere, and the leakage rate was measured as a function of pressure for pressure differentials of up to 25 in. of water. The data were fitted to empirical equations that describe the leak rate at any pressure differential within the range of the experimental tests. The forms of the equation… more
Date: June 20, 1960
Creator: Baurmash, L.; Burnett, F. C.; Koontz, R. L. & Nelson, C. T.
Partner: UNT Libraries Government Documents Department
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Preparation of Americium Dioxide by Thermal Decomposition of Americium Oxalate in Air

Description: One hundred and seventy five grams of americium in a hydrochloric acid solution varying from 1 to 7 N was converted to americium dioxide. Americium oxalate was precipitated from 0.1 N HCI with 100% excess oxalic acid and was converted to the dioxide by calcination at 800 ts C in air. The solubility losses in the oxalate precipitation filtrate averaged approximately 7 mg/liter of solution, with a total loss of 0.09%. (auth)
Date: December 20, 1960
Creator: Baybarz, R. D.
Partner: UNT Libraries Government Documents Department
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Travel to Oak Ridge and Savannah River Plant to Study Processing Plant Containment Philosophy. Trip Report, January 26--29, 1960

Description: This report discusses travel to the Oak Ridge National Laboratory on January 26 and 27 and the Savannah River Laboratory and Plant on January 28 and 29, 1960. The primary objectives of the trip were to obtain information on the containment philosophy for processing plants recently adopted by Oak Ridge National Laboratory and on the Palm Program at Savannah River.
Date: March 9, 1960
Creator: Beard, S. J. & Oberg, G. C.
Partner: UNT Libraries Government Documents Department
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Strontium-90: Recovery and lag storage interim program

Description: Increased interest in the civilian, space, and military applications of isotopic power has prompted a study by which the Chemical Processing Department can provide the interim strontium-90 requirements on a schedule considerably accelerated from that previously proposed. This document summarizes a study of the technical and operational feasibility and hazards involved in: recovery of semi-refined megacurie quantities of Sr{sup 90} from current Purex waste; lag storage of the Sr{sup 90} fraction… more
Date: August 2, 1960
Creator: Beard, S. J. & Swift, W. H.
Partner: UNT Libraries Government Documents Department
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HEAT-TRANSFER EXPERIMENTS ON A PROPOSED FUEL ASSEMBLY FOR THE EXPERIMENTAL GAS COOLED REACTOR. SECTION II FO FUEL-ASSEMBLY HEAT-TRANSFER AND CHANNEL PRESSURE-DROP EXPERIMENT FOR THE EGCR RESEARCH AND DEVELOPMENT PROGRAM

Description: Heat-transfer data are presented for the Experimental Gas Cooled Reactor Title I seven-rod fuel-assembly design. The effect on heat transfer of (1) the radial location of the outer six rods of the seven-fuel-rod cluster and of (2) the addition of helical-finned spacers at the midpoint of each of the seven fuel rods is discussed. The heattransfer data were obtained to verify preliminary general assumptions pertaining to the heat-transfer characteristics of the seven- rod fuel-assembly design and… more
Date: April 12, 1960
Creator: Beaudoin, C.L. & Higgins, R.M.
Partner: UNT Libraries Government Documents Department
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Bone Marrow Activity in Vitro Under the Influence of Anemic Serum and Human Erythropoietin

Description: A method is described for observing the uptake of Fe by rat bone marrow cells in vitro. Results of experiments on effects of anemic serum and human erythropoietin are presented with a brief discussion. It is concluded that the differences in uptake of Fe/sup 59/ are the result of isotope dilution. (auth)
Date: May 1, 1960
Creator: Beck, J. S.
Partner: UNT Libraries Government Documents Department
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Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 7 for April 1, 1960 to June 30, 1960

Description: High-temperature x-ray diffraction experiments provided confirming evidence regarding the origin of the metastable gamma phase and of the general features of the zirconiumhydrogen phase system. These experiments also showed that the reaction alpha + delta -- beta (the eutectoid reactlon on heating) proceeds at an extraordinarily slow rate, although the reverse reaction proceeds so rapidly that beta phase cannot be retained to room temperature by quenching. The sluggishness of the eutectoid reac… more
Date: July 1, 1960
Creator: Beck, R. L.
Partner: UNT Libraries Government Documents Department
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Research and Development of Metal Hydrides. Summary Report for October 1, 1958-September 30, 1960

Description: A detailed study of the fundamental relations in the zirconium -- hydrogen system was made in order to clarify the many points of dispute and to evolve a complete picture describing all phases of this system. An engineering evaluation was made of means for utillzing the various high cross-section metal hydrides in shielding or control applications. These materials would combine the processes of thermalization and absorption. Consequently, they are of considerable interest for use in shielding o… more
Date: November 1, 1960
Creator: Beck, R. L.
Partner: UNT Libraries Government Documents Department
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THE DIFFUSION OF RADIOACTIVE FISSION PRODUCTS FROM POROUS FUEL ELEMENTS

Description: The release of fission products from porous fuel elements during irradiation may be largely a diffusion process. An equivalent-sphere hypothesis was proposed to provide a model by which the diffusion can be analyzed. The equations of diffusion were previously solved for in- pile conditions. The slow convergence of the formulas makes the previous solutions awkward. In the present investigation alternate formulas were derived which are more suitable under certain circumstances. Tables were prepar… more
Date: April 18, 1960
Creator: Beck, S.D.
Partner: UNT Libraries Government Documents Department
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Operating Experience With the Sodium Reactor Experiment and Its Application to the Hallam Nuclear Power Facility

Description: The Sodium Reactor Experiment (SRE) was constructed to demonstrate the feasibility of sodium-oooled graphitemoderated reactors for central station power. The operating experience of SRE has provided valuable data for the design of the Hallam Nuclear Power Facillty (HNPF) now under construction. Some of the difficulties found in the SRE, which HNPF will be designed to avoid, are the sodium-sodium intermediate heat exchanger (horizontal position in SRE gave trouble; a vertical position will be us… more
Date: January 1, 1960
Creator: Beeley, R. J. & Mahlmeister, J. E.
Partner: UNT Libraries Government Documents Department
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The Sodium Graphite Reactor: Tommorrow's Power Plant

Description: A description is given of the Advanced Sodium Graphite Reactor Power Plant, including the reactor, heat transfer systems, generatirg plant, control systems, and the economics of producing 256 Mw(e). The safety of this design is due to its unusually low operating pressure, absence of chemically incompatible materials in the core, and excellent stability under atatic and dynamic conditions. The reactor is being constructed at Hallam, Nebraska, at a probable cost of 0 to 0/kw, exclusive of the fir… more
Date: April 25, 1960
Creator: Beeley, R. J.; Lowell, E. G.; Polak, H. & Renard, J.
Partner: UNT Libraries Government Documents Department
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The Salt Cycle Process

Description: The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the red… more
Date: August 1, 1960
Creator: Benedict, G.E.; Lyon, W.L.; Mudge, L.K.; Swanson, J.L. & Walling, M.T. Jr.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: July 1960

Description: This document presents a summary of work and progress at the Hanford Engineer Works for July, 1969. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project sections… more
Date: August 15, 1960
Creator: Bennett, C. A.
Partner: UNT Libraries Government Documents Department
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