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A Sequence for Predicting Waste Transport by Ground Water

Description: From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
Partner: UNT Libraries Government Documents Department
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Preliminary investigation of water coagulation characteristics as affects reactor effluent radionuclides

Description: Several theories have been advanced regarding the structure and characteristics of the aluminum hydroxide molecule when produced from alum in the water treatment process. The Water Treatment Task Force initiated this test to exploit a theory that increased adsorption of soil-leached elements, present in Columbia River water, by the floc particle would occur when the precipitate vas formed in its terminal pH state. This report discusses a half-plant test which was initiated at E Reactor Plant wh… more
Date: April 15, 1965
Creator: Frymier, J. W.
Partner: UNT Libraries Government Documents Department
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Battelle-Northwest Monthly Activities Report, March 1965

Description: This report covers progress in the following areas: production reactor support; plutonium recycle program; PRTR HPD core; corrosion and water quality; PRTR pressure tubes; reactor components development; plutonium ceramics research; ceramics (uranium) fuel research; swelling studies; irradiation damage to reactor materials; ATR gas loop studies; graphite studies; metallic fuel development; plutonium and U-233 fueling of a fast compact reactor; FFTF studies; radiation effects on metals; customer… more
Date: April 15, 1965
Partner: UNT Libraries Government Documents Department
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Physics and Instruments Department Monthly Report, July 1965

Description: This monthly document details activities of the Battelle-Northwest Physics and Instruments Department during the month of July 1965. (FI)
Date: August 15, 1965
Creator: Paul, R. S.
Partner: UNT Libraries Government Documents Department
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Tungsten Cladding of Tungsten-Uranium Dioxide (W-UO2) Composites by Deposition from Tungsten Hexafluoride (WF6)

Description: A program is being conducted to develop a process for cladding tungsten and tungsten cermet fuels with tungsten deposited from the vapor state by the hydrogen reduction of tungsten hexafluoride. Early work was performed using recrystallized, high purity, commercial tungsten as the substrate material. Temperatures in the range 660 to 12950F (350 to 1700°C) and pressures from 10 to 350 mm Hg were investigated. Hydrogen to WF 6 ratios of 10: 1 to 150: 1 were utilized. Efforts were directed toward… more
Date: February 15, 1965
Creator: Lamartine, J.T. & Hoppe, A.W.
Partner: UNT Libraries Government Documents Department
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SNAP 10A FSEM-3 Agena Compatibility Test

Description: From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.
Date: June 15, 1965
Creator: Teresa, M.
Partner: UNT Libraries Government Documents Department
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Carbide Fuels in Fast Reactors

Description: Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: June 15, 1965
Partner: UNT Libraries Government Documents Department
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Design, Construction, and Initial Operation of General Atomic In-Pile Loop

Description: From preface: To test the HTGR fuel-element design under environmental conditions of radiation, temperature, and pressure that approximate those in the Peach Bottom core and to test the operability of a dynamic system containing a vented graphite-clad fuel element.
Date: February 15, 1965
Creator: Simon, R. H.
Partner: UNT Libraries Government Documents Department
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Technical feasibility of using uranium oxide fuels at Hanford

Description: The use of uranium oxide fuel and the dispensing with metallic fuel elements in the Hanford production reactors have been contemplated in the past but have not been examined in any detail. This report reviews the technical feasibility of using oxide fuel and discusses the reactor limitations and changes in plutonium and isotope production. These results are based on preliminary calculations and a research and development program would be required to establish the validity of the calculated valu… more
Date: February 15, 1965
Partner: UNT Libraries Government Documents Department
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Reactor and Materials Technology monthly report 02 Program, November 1965

Description: Metallic fuel development is reported concerning N-reactor fuel element failures, target element development, target element closure welds, alternate target element closure systems, alternate uranium compositions, N-fuel support development, hot die size fuel cladding, improved closures for ThO{sub 2} elements, and N-reactor meltdown tests in the IRP. Corrosion and water quality studies are proceeding with emphasis on downstream pitting of aluminium process tubes, hydride formation in zircaloy … more
Date: December 15, 1965
Creator: Albaugh, F. W.
Partner: UNT Libraries Government Documents Department
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Status of plant assistance irradiations as of May 14, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of May 14, 1965. The report covers the status of material undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes.
Date: June 15, 1965
Creator: Ferguson, J. H.
Partner: UNT Libraries Government Documents Department
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Iron-masonite shield attenuation effectiveness status report

Description: This is the fifth in a series of reports presenting the status and deterioration rates of the B. D, DR, F, and H biological shields. The last previous reports covering the period 1959 through March 31, 1961, indicated no significant decreasing trends in the attenuating effectiveness of the biological (iron-masonite) shields. At that time the combination of increasing average helium percentages and adding fringe poison in the smaller reactors resulted in corresponding reductions in shield temper… more
Date: April 15, 1965
Creator: Gross, P. D.
Partner: UNT Libraries Government Documents Department
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Fuel element hole location survey

Description: No Description Available.
Date: June 15, 1965
Creator: Fatzer, E.G. & Sturtevant, J.
Partner: UNT Libraries Government Documents Department
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