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GAS-PRESSURE BONDING OF FLAT-PLATE FUEL ASSEMBLIES

Description: subscale fiat-plate fuel subassemblies measuring up to 2 by 2 by 20 in., incorporating 16 Zircaloy-2-clad uranium -zirconium fuel plates and 15 coolant channels, were successfully fabricated by the gas-pressurebonding process. Autoclave design, specimen-container configuration, and the design and preparation of specimen components were among the problems studied. Uneven heating of the bonding specimen, caused in part by convective heat transfer, was minimized by developing a special four-elemen… more
Date: January 20, 1959
Creator: Paprocki, S.J.; Hodge, E.S.; Boyer, C.B. & Getz, R.W.
Partner: UNT Libraries Government Documents Department
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Irradiation program for candidate 105-N graphites

Description: Selection of new graphites for nuclear reactor moderator applications can be accomplished either by: (1) an evaluation of the behavior of untested materials processed by proven methods of manufacture when tested under conditions typical of the proposed application, or, (2) a development program exploring new materials, processes and environments which results in graphites meeting or exceeding design requirements. The latter approach is not easily adapted to construction schedules and therefore … more
Date: January 20, 1959
Creator: Woodruff, E. M.
Partner: UNT Libraries Government Documents Department
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LIST OF PARTICLE-ACCELERATOR INSTALLATIONS: ADDENDA AND ERRATA

Description: A list of particle-accelerator installations, giving location, type, dimensions, particles accelerated, and energy, is presented. (A.C.)
Date: January 20, 1959
Creator: Behman, G.A.
Partner: UNT Libraries Government Documents Department
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REQUIREMENTS FOR RAW MATERIALS IN AN EXPANDING NUCLEAR POWER ECONOMY

Description: The need for breeding does not appear to be highly cost for a moderately optimistic expanding nuclear power economy between 1960 and 2000. Since the expansion rate of the US nuclear economy is assumed to be high at least 2/3 of the U-235 recovered from natural uranium is used to supply reactor inventory. It is the remaining 1/3 of the available U-235 that can be saved by breeder breeders or a breeder and converter are the doubling time and a parameter expressing the total fissile inventory per … more
Date: January 20, 1959
Creator: Arnold, E.D. & Ullmann, J.W.
Partner: UNT Libraries Government Documents Department
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Revised hazards study -- Underground storage of radioactive liquid wastes

Description: This report discusses risks associated with the underground storage of high-level radioactive wastes from the Purex Plant at Hanford in 1957. Radiation doses and contamination of the Columbia River resulting from storage tank leaks are discussed.
Date: January 20, 1959
Creator: Haney, W. A. & Linderoth, C. E.
Partner: UNT Libraries Government Documents Department
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Variable goal equations for enriched and natural I and E material at the C and K Reactors

Description: We have previously transmitted interim recommendations of goal exposure plans for enriched I&E material at the C and K reactors and for natural I&E material at the K Reactors. We indicated in the references that corrections for changes in inlet temperature would be forthcoming. The purpose of this letter is to transmit revised goal exposure equations.
Date: January 20, 1959
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: January 1959

Description: This report for January 1959, 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; and employee relations.
Date: February 20, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly record report, January 1959

Description: This document details activities of the irradiation processing department during the month of January 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering operation; Employee Relations Operation; and Financial Operation.
Date: February 20, 1959
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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THE NUCLEAR FUEL CYCLE: PROSPECTS FOR REDUCING ITS COST

Description: Nuclear fuel cost of 1.25 mills/kwh would make nuclear power competitive with conventional power in lowcost coal areas if capital and operating costs can be brought to within about 10 percent of those of coal-fired plants. Substantial decreases in fuel fabrication cost are anticipated by 1970: other costs in the fuel cycle are expccted to remain about the same as at present. Unit costs and irradiation levels that would be needed to give a fuel cost of 1.25 mills/kwh are believed to be attainabl… more
Date: February 20, 1959
Creator: Albrecht, W.L.
Partner: UNT Libraries Government Documents Department
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Thermal Bowing of Core Subassemblies

Description: Report issued by the APDA over studies conducted on thermal bowing of core sub-assemblies at the Enrico Fermi Atomic Power Plant. As stated in the introduction and summary, "the present report deals with this problem in the design of the Enrico Fermi Reactor and with the method which has been adopted to avoid a positive temperature coefficient of reactivity" (p. 1). This report includes illustrations, and photographs.
Date: February 20, 1959
Creator: De Stordeur, Arnold
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: February 1959

Description: This report for February 1959, 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; and employee relations.
Date: March 20, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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HIGH FLUX ISOTOPE REACTOR PRELIMINARY DESIGN STUDY

Description: A comparison of possible types of research reactors for the production of transplutonium elements and other isotopes indicates that a flux-trap reactor consisting of a beryllium-reflecteds light-water-cooled annular fuel region surrounding a light-water island provides the required thermal neutron fluxes at minimum cost. The preliminary desigu of such a reactor was carried out on the basis of a parametric study of the effect of dimensions of the island and fuel regions heat removal rates, and f… more
Date: March 20, 1959
Creator: Lane, J. A.; Cheverton, R. D.; Claiborne, G. C.; Cole, T. E.; Gambill, W. R.; Gill, J. P. et al.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, February 1959

Description: This document details activities of the irradiation processing department during the month of February 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: March 20, 1959
Partner: UNT Libraries Government Documents Department
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Neutron and Gamma Flux Attenuation in a Withdrawn SRE Control Rod

Description: An investigation was made of the neutron and gamma flux distribution along the entire length of a withdrawn control rod in the SRE in order to determine heating, activation and dose rates produced by the streaming neutrons and gammas.
Date: March 20, 1959
Creator: Horst, K. M. & Aline, P. G.
Partner: UNT Libraries Government Documents Department
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Recent developments in feed preparation and solvent extraction

Description: For presentation at the 5th Nuclear Congress, Clevelands Apr. 7, 1959. Increasing emphasis has been placed recently on the application of solvent extraction to the recovery of uranium and plutonium from spent power reactor fuels. Zircaloy-2 jackets were removed from PWR blankettype fuels by dissolution with the Zirflex Process, and the UO/sub 2/ cores were dissolved in 10 M HNO/sub 3/. Zirflex treatment of prototype samples irradiated to 2500 Mwd/ ton resulted in satisfactory dissolution rates … more
Date: March 20, 1959
Creator: Bruce, F. R.; Blanco, R. E. & Bresee, J. C.
Partner: UNT Libraries Government Documents Department
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An Automatic Water Deaeration System

Description: Laboratory studies involving fluid flow through porous media require use of fluids having low dissolved gas content. Water is the major fluid used in various and box model and soil permeability studies carried out by the Geochemical and Geophysical Research group. Tap water supplied to the 222-U Bldg. contains a large amount of dissolved air. Under the reduced pressure encountered during model studies, the air is released from solution and gradually clogs the pores of the sand or other porous m… more
Date: April 20, 1959
Creator: Raymond, J. R.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, March 1959

Description: Production of Pu, UO{sub 3}, and Pu metal exceeded forecasts. The 2nd attempt at Purex to recover Zr-Nb resulted in about 1/3 recovery, contaminated with about 1% of the Ce. Palm losses to Purex U product were eliminated, and the Pu content was reduced 5 to 10{times}. Routing the dissolver rinses into 3WB concentrator resulted into improved rinsing efficiency. Unclarified feed was processed through Purex HA column. In a test for using B in Redox, the B was routed completely to the waste; it was… more
Date: April 20, 1959
Partner: UNT Libraries Government Documents Department
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Corrosion of 2R-2 and 304 Stainless Steel Following the Turco-4501 Decontamination Process.

Description: The build up of contaminated film on the internal surfaces of high temperature in-reactor recirculating water loops has created serious radiation exposure problems to operational and maintenance personnel. A considerable amount of work has been applied to develop an effective decontamination process for the decontamination of these loops and their components.
Date: April 20, 1959
Creator: Larrick, A. P. & Lotsinger, R. J.
Partner: UNT Libraries Government Documents Department
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PREDICTED VAPOR PRESSURES IN THE HRT

Description: Radiolytic gas concentration in the HRT as a function of operating power and temperature have been calculated for the conditions of Run 18. The partial pressure of the radiolytic gas was estimated for the various conditions. The maximum total vapor pressure (the maximum summation of the radiolytic gas partial pressures excess oxygen partial pressures and D2O vapor pressure) was found to exist at the core and blanket outlets for all avcrage temperatures greater than 250 C. Below 240 C at some re… more
Date: April 20, 1959
Creator: Gift, E.H.
Partner: UNT Libraries Government Documents Department
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PRTR Gas-Cooled Loop, Hazards Survey of Preliminary Scope Design

Description: The Atomic Energy Commission has recently developed an enlarged program for the study of graphite moderated, gas cooled power reactor systems. It has been recognized, however, that understanding of radiation damage and radiation induced chemical reactions of graphite at the proposed high moderator temperatures is inadequate and that improved understanding is essential if the design of such reactors is to be optimized. Accordingly, the Atomic Energy Commission requested Hanford to organize a mod… more
Date: April 20, 1959
Creator: Wittenbrock, N. G.
Partner: UNT Libraries Government Documents Department
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Sample Connector and Cable Radiation Measurements. Test Results DL-S-260-S (RNI-9). Section I

Description: The purpose of the test was to determine total radioactivity due to activation and possible contamination of six special connectors and a length of cable suspended in Nuclear Instrument Channel D source range detector well during the performance of the second Reactivity Lifetime Test. This data was to be used to estimate the effective gamma and beta-gamma activity half lives of the sample. The effective gamma and beta gamma half lives of the samples cannot be determined from the information ava… more
Date: April 20, 1959
Creator: Price, F. C.
Partner: UNT Libraries Government Documents Department
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Sodium Fluoride as a Spectroscopic Carrier for Plutonium Metal Analysis

Description: A pyroelectric carrier distillation method, using sodium fluoride as a spectroscopic carrier, was developed for the impurity analysis of plutonium metal. (auth)
Date: April 20, 1959
Creator: Johnson, A. J. & Vejvoda, E.
Partner: UNT Libraries Government Documents Department
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