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Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report

Description: An analytical trajectory and aerothermodynamic analysis of a satellite containing a Task 2 thermoelectric generator was completed. A 300-statute mile circular polar orbit was used for this analysis and the launch was assumed to be from Vandenberg Air Force Base. Results of this study show that upon natural decay from a successful mission, the radio-cerium fuel will burn up in space at high altitude, thus only a very minor amount of radio cerium will be released to the stratosphere. A complete a… more
Date: December 27, 1960
Creator: Oehrli, R.
Partner: UNT Libraries Government Documents Department
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REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report

Description: A study was made of two problems of salt-cavity storage, namely, seepage of wastes out of formations and closure of cavities due to plastic flow of salt. The results indicate that both problems are negligible; bedded salt is more impermeable than dome salt. Kerosene was found to be nonreactive with dome salt whereas brine solutions showed some interaction. It is concluded that storage of radioactive wastes in salt cavities is feasible. (D.L.C.)
Date: December 30, 1960
Creator: Reynolds, T.D. & Gloyna, E.F.
Partner: UNT Libraries Government Documents Department
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Feasibility Study of a New Mass Flow System : Quarterly Report No. 2 Covering the Period from September 1 to November 30, 1960

Description: This is the second quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: December 19, 1960
Creator: Burgwald, G. M.; Stone, C. A. & Genthe, William K.
Partner: UNT Libraries Government Documents Department
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Development and Evaluation of High-Temperature Tungsten Alloys : Final Report, October 1, 1960 - September 30, 1960

Description: This report summarizes investigations taken between October 1, 1959, to September 30, 1960 with the objectives of developing high-tungsten alloys which are readily fabricable into massive and complex shapes and which possess adequate strength for operation at temperatures up to 2000 F. Within this report, studies are divided into two main categories: alloy development and material fabrication techniques
Date: December 14, 1960
Creator: Holtz, F. C. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: November 1960

Description: This report, from the Chemical Processing Department at HAPO for November 1960, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and special separation processing and auxiliaries operation.
Date: December 21, 1960
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Semi-final report (report No. 3) E-N load conversion ratios

Description: Experimental data on plutonium yield and U{sup 235} burnout are now available on the E metal portion of three central zone striped E-N columns and one fringe blanket E column. These data and an overall E-N load conversion ratio based on experimental data are now reported.
Date: December 22, 1960
Creator: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Loading and operating conditions for NIN-1 and NIE-1 elements in the KER loops under PT-IP-377-A

Description: This document provides the loading and operating conditions for eight 16-inch or five 24-inch elements, either natural NIN-1 or .947% enriched NIE-1, in any of the four KER loops. The loadings are tabulated; operating conditions for either charge in KER 2, 3, 4, or 1 are given in figures.
Date: December 23, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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PT-IP-385-C, E-N reactivity matching measurement

Description: The projected E-N load at H Reactor will require a complete change in the type of charge placed in most flattened zone process tubes. Objective of this test is to determine the reactivity of the proposed E-N charge relative to the known natural uranium charge reactivity.
Date: December 30, 1960
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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KER-4 operating report test K-4-8, PT-IP-300-A

Description: Objective of the test was to determine and evaluate the behavior of 8 20-inch fuel elements during irradiation using the hot-headed end closures on the inner tube.
Date: December 29, 1960
Creator: Young, K. L.
Partner: UNT Libraries Government Documents Department
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Discussion-preliminary review of the safety aspects of the crossunder line, Project CG-884. Volume 1

Description: In order to reduce both charge-discharge shutdown time and the number of manhours of radiation exposure, Project CGI-884 is being completed at the B, D, DR, F and R Reactors. This consists essentially of installing a large drain line at the bottom of one rear reactor riser. This drain line passes to a control valve and then to the effluent line beyond the downcomer. This system by-passes the crossover downcomer part of the effluent system and eliminates the need for intermittent rear crossheade… more
Date: December 19, 1960
Creator: Jones, S. S.
Partner: UNT Libraries Government Documents Department
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K Reactor: HCR sleeves

Description: Irradiation Processing Department opinions regarding HCR sleeves. It is believed that Zr-2 would be a satisfactory sleeve material providing it is limited to maximum service temperatures the order of 400 degrees C. Both Inconel and a 300 series stainless steel are believed possibilities for uncooled sleeve materials, with Inconel our preference. Beryllium, in virtue of its outstanding nuclear properties and probably satisfactory chemical and mechanical properties, warrants consideration on a pi… more
Date: December 12, 1960
Creator: Zima, G. E.
Partner: UNT Libraries Government Documents Department
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Revisions to variable goal exposure plans for production type fuel elements

Description: The exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle. When metal throughput in limited by ex-reactor physical capabilities to a level lower than the unrestrained requirements, exposures higher than those recommended in this document would be indicated. In essence then, these plans represent minimum economical exposures f… more
Date: December 6, 1960
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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[Hanford weekly teletype report]: Supplement report for week ending June 12

Description: This document contains information about flooding of the Columbia River. It focuses attention on the following; increased elevation due to rainfall, seepage which destabilized the constructed dike, flooding of cellars, evacuation of people to emergency shelters, tug boat collision damage to power lines, and the washout of the Van Giesen Street Bridge on Yakima River.
Date: December 31, 1960
Partner: UNT Libraries Government Documents Department
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Optimum canning conditions for four-inch I & E fuel elements

Description: Because of difficulties in charging eight-inch fuel elements in bowed process tubes in the upper parts of the old reactors, IPD has requested that four-inch I & E fuel elements be provided for these tubes early in CY1961. Approximately 30,000 fuel elements of this design, Model OVN, will be required per year. Since most of these fuel elements will be charged in the upper fringe zones, they will be in-reactor for an extended period of time. For this reason, the quality of this material should be… more
Date: December 20, 1960
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Analysis of E-N loadings

Description: Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were t… more
Date: December 28, 1960
Creator: Zimmer, W. H.
Partner: UNT Libraries Government Documents Department
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Control of radio-iodine emissions from the separations plants

Description: The release of radio-iodine from the irradiated uranium during dissolution, and the emission of a portion of this radio-iodine to the environs via the separations plant stacks continues to be a problem in spite of the expenditure of several million dollars for equipment designed to remove the radio-iodine from the gaseous wastes. This report discusses the control of the radio-iodine emissions from the hanford separation processes.(JL)
Date: December 19, 1960
Partner: UNT Libraries Government Documents Department
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Reconnaissance for Uranium in the Arica Area, Province of Tarapaca, Chile

Description: Abstract: In August 1958 two geologists of the Instituto de Investigaciones Geológicas de Chile made a one-week reconnaissance for uranium of the Arica area in northern Chile.
Date: December 1960
Creator: C., Mario Serrano & H., Erik Klohn
Partner: UNT Libraries Government Documents Department
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Vapor Pressures of the Rare Earths

Description: Abstract: This report presents the vapor pressures versus temperature data graphically for the rare earth elements, yttrium and scandium.
Date: December 23, 1960
Creator: Beavis, L. C.
Partner: UNT Libraries Government Documents Department
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Rear-face Parker fitting reaming

Description: Although a fuel reactor job procedure has not yet been prepared, techniques and equipment used in a current production test are adequate with minor modifications for full reactor Parker fitting reaming. With existing reactor hardware, available flow increases at B, D, and F Reactors would be limited to about 2,500 gpm. The extent of additional rear face piping problems which may be encountered as a result of reaming cannot in several instances be predicted with confidence at this time. It is ex… more
Date: December 6, 1960
Creator: Brinkman, L. B. & Corley, J. P.
Partner: UNT Libraries Government Documents Department
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Fuel element study for Reactor Overbore Program

Description: Recent studies have confirmed that large incentives exist for overboring the reactor process channels approximately 500 mils in the C and five old reactors under the proposed Plant Improvement Program. Conservative estimates of the incentives for overboring indicate a payout period of about two years for the proposed work, an increase in plutonium production of 15--18%, derived from increased conversion ratio and a reduction in plant unit cost. Since sufficient progress has been made in the are… more
Date: December 15, 1960
Creator: Stringer, J. T. & Blanton, W. A.
Partner: UNT Libraries Government Documents Department
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