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Extraction of tritium from (LiAlO{sub 2}) targets

Description: This paper describes procedures which relate to the process of extracting tritium from irradiated lithium aluminate target elements.
Date: April 10, 1967
Creator: Cooperstein, R.
Partner: UNT Libraries Government Documents Department
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Pacific Northwest Laboratory Monthly Activities Report for July 1967

Description: This monthly report details activities of the Battelle Pacific Northwest Laboratory in production and Hanford Plant assistance programs for the month of July 1967.
Date: August 1, 1967
Creator: Paul, R. S.
Partner: UNT Libraries Government Documents Department
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K Reactor graphite temperature economics relative to helium loss rates

Description: The purpose of this report is to present the results obtained from a study to determine the most economic K Reactor graphite temperature for assumed helium loss rates and the economic incentives for reducing the helium gas losses at these reactors.
Date: August 20, 1967
Creator: Newell, L. J.
Partner: UNT Libraries Government Documents Department
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Laboratory Studies of Al-Ni-U Bonding: Interim Report

Description: The purpose of this report is to summarize laboratory work concerning Al-Ni-U bonding. It was initiated by an analysis of the literature and hot die size bonding in particular. A hot die size bond has three major deficiencies. It is possible that one or more of the deficiencies could be alleviated by adjusting the hot die size bonding conditions, but most likely at the expense of aggravating the other deficiencies. To date the HDSB process has been superbly engineered to yield a high quality bo… more
Date: November 1, 1967
Creator: Gurwell, W. E.
Partner: UNT Libraries Government Documents Department
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Dissolver operation and metal transfer

Description: This report provides data on daily dissolver operation and metal transfers. Sodium hydroxide and sodium nitrate requirements are also given.
Date: October 12, 1967
Creator: Beaulieu, O. F.
Partner: UNT Libraries Government Documents Department
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A method to simulate interchannel flow through fuel element junctions during laboratory tests on a C-Reactor fuel model

Description: Interchannel flow through fuel element junctions can occur in production reactor fuel columns as a result of different pressure loss patterns in the two coolant subchannels. This interchannel flow is most significant during boiling conditions because, generally, the boiling length in each subchannel is different. These different boiling lengths result in divergent pressure loss characteristics in the subchannels and cause differential pressures to exist across the fuel element junctions. These … more
Date: October 4, 1967
Creator: Sutey, A. M.
Partner: UNT Libraries Government Documents Department
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Determining acceptable stack concentrations for gaseous wastes released to the atmosphere

Description: The following information is provided to assist you with your engineering evaluation of the gaseous wastes released to the atmosphere via stacks and roof vents in the 200 Areas for inclusion in the Hanford Low Level Waste Management Reevaluation Study report. Included in discussion are: release rates and public radiation dose rates.
Date: November 7, 1967
Creator: Brown, D. J.
Partner: UNT Libraries Government Documents Department
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MFC study - krypton and xenon recovery

Description: As commercial fuels reprocessing develops, large quantities of radioactive and stable fission rare gases will become available. These gases pose both a problem and an opportunity. When efficient methods of control and recovery are developed, the cost of these materials will be greatly reduced. With increased availability and reduced costs, commercial and government applications would be accelerated. Thus the fission gases which present potential environmental problems, would become useful by-pr… more
Date: November 8, 1967
Creator: Shaw, H. P.
Partner: UNT Libraries Government Documents Department
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Pacific Northwest Laboratory monthly activities report, August 1967

Description: This monthly activity report summarizes work done by the staff of Battelle-Northwest in support of the Division of Production and assistance programs directed by the Hanford Plant. The report is divided into four sections: direct AEC sponsored programs; assistance to Douglas United Nuclear; assistance to Isochem; and technical assistance to the Hanford Plant. The work is wide ranging, from environmental monitoring and remediation, to process development, fuel fabrication and studies, metallurgy… more
Date: September 1, 1967
Creator: Paul, R. S.
Partner: UNT Libraries Government Documents Department
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A preliminary evaluation of the thermal effects of the Ben Franklin Dam project on Columbia River temperatures below the Hanford Plant

Description: The planned construction of the Ben Franklin project below the Hanford production reactors poses the question of determining to what extent this project will affect the Columbia River temperatures. Using the plant operations record for the year 1966, and the weather record for the same period, a series of simulation runs was made to determine the effects of the clam on the temperature regime, and the extent to which density currents could be expected to develop. This information is to be used a… more
Date: November 1, 1967
Creator: Jaske, R. T.
Partner: UNT Libraries Government Documents Department
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Thermal mapping of the Columbia River at Hanford using an infrared imaging system

Description: The infrared imagery data was collected September 13, 1966 from 1010--1013 o`clock, using a mercury-doped germanium detector which was filtered to respond to wave lengths of infrared radiation. The magnetic-tape recorded information was processed with a computer program to obtain quantitative evaluations of river temperature variations and to accurately define surface temperature patterns resulting from the discharge of reactor effluents into the river. The river surface-temperature information… more
Date: February 28, 1967
Creator: Eliason, J. R.
Partner: UNT Libraries Government Documents Department
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K-Reactor: Loss of coolant temperature study of the biological skin

Description: It is of interest to investigate the time following a complete loss of coolant incident when the pile would be exposed to the ambient air. This is of concern due to the fast propagation of graphite burn-up when brought in contact with air at or above the operating temperature of the graphite (1292{degree}F). One possible way conjectured in which the pile can be exposed to the surrounding environment is for the centering flange gasket (neoprene) or the bellows gas seal (silicone) to fail. This p… more
Date: October 13, 1967
Creator: White, J. A.
Partner: UNT Libraries Government Documents Department
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Composition of ending inventory, January 1967

Description: This report provides Source and Special Nuclear Material composition of Ending Inventory Reports for the month of January, 1967.
Date: February 15, 1967
Creator: Budd, R. O.
Partner: UNT Libraries Government Documents Department
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Impact of proposed Washington State water quality standards on Hanford

Description: On November 17, 1967, the Atomic Energy Commission prepared a proposal the permissible incremental increase in the Hanford reach of the Columbia River. This report presents graphs and formulas that were considered in preparing this proposal.
Date: November 17, 1967
Creator: Corley, J. P. & Selby, J. M.
Partner: UNT Libraries Government Documents Department
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Lithium-aluminum separations request

Description: A test irradiation of lithium was recently completed in one of the Hanford K Reactors. It is requested that these lithium-aluminum alloy targets be separated and analyzed for tritium content. This request is for the analysis to be performed on two groups or batches of samples. The first group would be 38 elements with a total gas content estimated to be approximately 97 liters. The second batch would consist of 76 elements with a total gas content estimated to be approximately 193 liters. This … more
Date: November 10, 1967
Creator: Ambrose, T. W.
Partner: UNT Libraries Government Documents Department
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An analysis of hot die size fuel bonding

Description: A critical analysis of the Al-Ni-U bond and the hot die size bonding technique is given as the result of a literature search. Metallurgical aspects of the bond and the technique of hot die sizing are commented upon in particular.
Date: August 1, 1967
Creator: Gurwell, W. E.
Partner: UNT Libraries Government Documents Department
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Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1967

Description: Areas of work reported include: general radiation effects; toxicity of radioelements; combating detrimental effects of radiation; studies at the molecular and cellular level; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.
Date: March 1, 1967
Creator: Fawcett, S. L.
Partner: UNT Libraries Government Documents Department
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Zirconium hydride formation in Hanford production reactor process tubes

Description: Examination of Zircaloy-2 process tubes from Hanford Production Reactors has revealed extensive zirconium hydride formation. In general, attack is limited to the downstream portions of tubes where aluminum spacers are located. Most of the hydride platelets are contained in a case or layer on the inner surface of the tube. It is not unusual to find cases 0.004 to 0.005 in. thick. Analyses of the 0.037 in. wall tubes with such cases intact often reveal hydrogen concentrations greater than 1000 pp… more
Date: December 1, 1967
Creator: Winegardner, W. K. & Griggs, B.
Partner: UNT Libraries Government Documents Department
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