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A-11 seven cluster model: FFL-10 solid core tests

Description: This report summarizes the results of the seventh and last of a series of tests completed in the A-11 test program during the Contract Year 1964
Date: December 18, 1964
Creator: Cherish, P. & Leff, G.J.
Partner: UNT Libraries Government Documents Department
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The 25-Inch Liquid Hydrogen Bubble Chamber

Description: No Description Available.
Date: May 25, 1964
Creator: Barrera, F.; Byrns, R. A.; Eckman, G. J.; Hernandez, H. P.; Norgren, D. U.; Shand, A. J. et al.
Partner: UNT Libraries Government Documents Department
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100-KEW coolant backup adequacy

Description: No Description Available.
Date: April 29, 1964
Creator: Heacock, H. W.
Partner: UNT Libraries Government Documents Department
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105-F intermediate range test hole parameters

Description: This report discusses 105 intermediate range test hole which was bored in 105-F to demonstrate reactor hole boring techniques. This test hole was then utilized to determine the performance of neutron sensitive gamma compensated ion chambers (CIC), the effectiveness of epoxy reactor shield plug designs, the compatability of the prototype.components intermediate range instrumentation, and demonstrate the performance of an intermediate range monitor system on a typical Hanford reactor application. In the process of determining the above information physical, nuclear, gamma, and temperature data was recorded as related to the 105-F intermediate range monitor test hole and is provided in this report.
Date: November 16, 1964
Creator: Erickson, G. L.
Partner: UNT Libraries Government Documents Department
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241-SX tank farm waste storage

Description: Salt wastes from the Redox solvent extraction process have been routed to the 241-SX tank farm for storage since May 21, 1954. Tanks in this farm contain wastes from three types of irradiated uranium processing: (1) low (approximately 250 MWD/T) and (2) high (approximately 600 MWD/T) natural uranium; and (3) E-metal. It is estimated that approximately 1.6 Kgs of Am-Cm, 17 Kgs of Np-237, 20 Kgs of Pu and 8 tons of uranium are present in the sludges from wastes generated through 4-30-64. A total of 12.1 Kgs of the 29.1 Kgs of Np-237 estimated has been recovered or is present in the Redox Np-237 accumulation cycle as of 4-30-64. Because of the potential for unmeasured losses (such as Pu or U precipitates) the total plutonium and uranium may exceed the quantities stated herein. A breakdown of the estimates by tanks is provided.
Date: September 3, 1964
Creator: Hanson, G. L.
Partner: UNT Libraries Government Documents Department
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500-Thgc--a 500 Node Transient Heat Transfer Code

Description: This document is a user manual for those who are familiar with problems 500 Node Transient Heat Transfer Code.
Date: March 27, 1964
Creator: Blaine, R. A. & Berland, R. F.
Partner: UNT Libraries Government Documents Department
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1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2

Description: From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Date: February 14, 1964
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3

Description: From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
Date: February 14, 1964
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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1000-Mwe SGR. 90% ThO₂, 10% UO₂ Alternate Fuel Core Thermal and Hydraulic Analysis

Description: The thermal and hydraulic core parameters were determined using the SORTD I code for 90% ThO/sub 2/, 10% UO/sub 2/ fuel both for (1) a core containing 592 fuel elements corresponding to the UC reference core with a maximum UC temperature of 2000 deg F and (2) a core containing 784 fuel elements corresponding to a UC core with a maximum UC temperature of 1750 deg F. Eighteen rod elements with 2.5 in./sup 2/ and 3.5 in./sup 2/ fuel areas, and 30 rod elements with 4.5 in./sup 2/ and 5.5 in./sup 2/ fuel areas are analyzed for 8 cases. (auth)
Date: February 19, 1964
Creator: Imig, J. K.
Partner: UNT Libraries Government Documents Department
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6144-Channel Time-of-Flight Analyzer

Description: Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Partner: UNT Libraries Government Documents Department
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630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 7

Description: This progress report covers the period from November 15, 1963 to February 15, 1964. A study indicated that the most desirable type of blower drive turbine is one using main turbine throttie steam conditions and exhausting to the main turbine cross-over line. Preliminary planning for the initiation of a dynamic structural analyses of the overall steam generator was completed. External pressure loading and thermal stress calculations show that the calandria has a suitable design margin. A revised fuel latch operable from the rear face of the core was designed. A study was initiated to determine the feasibility of substituting Zircaloy for the stainless steel tubing within the active core. Preliminary sizing of control rod extensions and gang plates was completed. Initial loading of the second configuration of the 630A critical experiment reactor was completed. Detailed power distributions were measured in the 11 typical positions. Subcritical and critical rod worth curves were obtained in the critical experiment with up to 132 shim rods in the core. Moderator temperature coefficient measurements were made and agreed well with analytical data. Critical experiment correlation of fine radial power calculations in the revised mock-up showed good agreement. Performance specifications were prepared for a 1-Mw(e) power plant. Parametric thermal analyses, based on various tube sheet thicknesses and heating rates, were completed for the top and bottom tube sheets. The shield plug was redesigned to accommodate additional shim rods and to facilitate fabrication and moderator flow adjustments. Calculations of the operating and shutdown dose at the nuclear sensor location was started. Studies were performed to determine the size of the port openings needed to prevent buckling in the containmert vessel in the event of ship sinking. A blower shaft static seal was built and tested with satisfactory results. Manufacture and procurement of all parts for two developmental …
Date: March 16, 1964
Partner: UNT Libraries Government Documents Department
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ABSORPTION CHANGES IN BACTERIAL CHROMATOPHORES. II. A NEWCHLOROPHYLL-LIKE PIGMENT FROM THE OXIDATION OF CHROMATOPHORES FROMRHODOSPIRILLUM RUBRUM

Description: Evidence is presented which points to (at least) two bound forms of bacteriochlorophyll present in chromatophores of Rhodospirillum rubrum, both of them readily converted to unbound bacteriochlorophyll (abs. max. 770 mu) when the chromatophores are extracted with acetone or ethanol. Controlled oxidation of the chromatophores with Ir(IV) or with Zn(II) and ferricyanide preferentially destroys the more strongly absorbing pigment (abs. max. 880 mu) but brings about only a slight decrease in the magnitude of the photoinduced absorption changes at 810 and 792 mu. Such oxidations yield a new pigment, absorbing at 715 mu in the aqueous preparation and, more strongly, at 680-684 mu when the pigment is extracted into organic solvents. This pigment is formed irreversibly and is therefore different from the material formed by photooxidation of chromatophores. Its visible spectrum and the spectrum of the material formed from it by acidification suggest that it is a chlorophyll-like substance, possibly derived from bacteriochlorophyll by (two-electron) oxidation of one of the dihydropyrrole rings to a pyrrole ring. Directions are given for separation of this pigment from other colored compounds present in the oxidation mixtures.
Date: October 1, 1964
Creator: Gould, Edwin S.; Kuntz Jr., Irwin D. & Calvin, Melvin
Partner: UNT Libraries Government Documents Department
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Acceptance test specifications for accelerometers, 1964, September 22

Description: This document outlines the Westinghouse Astronuclear Laboratory (WANL) specification and procedures for acceptance testing of accelerometers. All accelerometers that are to be used for reactor instrumentation shall meet the requirements of this specifications before being accepted.
Date: September 22, 1964
Creator: Burlas, T. C. & Karako, E. F.
Partner: UNT Libraries Government Documents Department
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Acceptance test specifications for pressure transducers, 1964, September 23

Description: This document outlines the Westinghouse Astronuclear Laboratory (WANL) specifications and procedures for acceptance testing of differential and absolute pressure transducers. All pressure transducers used for reactor instrumentation shall meet the requirements of this specification before being accepted .
Date: September 23, 1964
Creator: Burlas, T. C. & Karako, E. F.
Partner: UNT Libraries Government Documents Department
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Accurate Nuclear Fuel Burnup Analyses; Ninth Quarterly Progress Report, (December 1963 - February 1964)

Description: The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: March 1, 1964
Creator: Rider, B. F.; Peterson, J. P., Jr.; Ruiz, C. P. & Smith, F. R.
Partner: UNT Libraries Government Documents Department
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