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Liquid Metal Fast Breeder Reactor Design Study

Description: From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."
Date: January 1964
Partner: UNT Libraries Government Documents Department
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Design and Construction of a Desalination Pilot Plant, a Reverse Osmosis Process

Description: Report containing plans for a desalination pilot plant for the purposes of evaluating the feasibility of reverse osmosis for the desalination of sea and brackish water with the capacity of 1,000 gallons of potable water produced per day.
Date: January 1964
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
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Process Heat Reactor Program. Quarterly progress report, February 1-April 30, 1964

Description: Work was continued on the development of a process for the gasification of bituminous coal with heat from a nuclear reactor. Major objectives of the project are: (1) develop and test components for a gas-cooled reactor system that can heat gases to 2000/sup 0/ to 2500/sup 0/F; (2) investigate coal gasification methods compatible with this system; and (3) develop an exchanger that can utilize high-temperature heat to gasify coal or heat chemical process streams. During the past year, work was co… more
Date: January 1, 1964
Partner: UNT Libraries Government Documents Department
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Precipitation of cerium sulfate

Description: Cerium sulfate purified by D2EHPA in Semiworks can be precipitated by adjusting pH to between 1 and 2 in tank 6 with 50% caustic. The solution can then be transferred through tank 1 to tank 67, where sodium bisulfate is added to make the solution 0.5M sulfate. A stoichiometric amount (mole for mole) of 50% caustic is added to just neutralize the sodium bisulfate. The precipitate is digested one hour at 60 C, then filtered.
Date: January 27, 1964
Creator: Buckingham, J. S.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: December 1963

Description: This document details activities of the irradiation processing department during the month of December, 1963. 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; and Financial Operation.
Date: January 14, 1964
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories monthly activities report, December 1963

Description: The monthly report for the Hanford Laboratories Operation, December 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operations are discussed.
Date: January 15, 1964
Partner: UNT Libraries Government Documents Department
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Uranium burnout values

Description: Attached is the interpolated uranium burnout values for .570% through 3.000% U-235. Due to increasing interest in higher U-235 values, this document was issued to replace HW-77929 which contained values to 1.519% U-235. The source data was based on the Reactor Cost Studies burnout schedule obtained from Washington -- AEC.
Date: January 30, 1964
Creator: Smith, W. G.
Partner: UNT Libraries Government Documents Department
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End closure of hot die size diffusion bonded fuel elements

Description: Studies initiated at Hanford in 1961 for the purpose of developing an alternate cladding process for I&D fuel elements for the eight existing production reactors indicated that the hot die sizing diffusion bonding process offered the greatest incentive. Hot die sizing was the most attractive with respect to improved fuel quality and potential reduction in fuel element unit cost when compared to the existing AlSi brazing process. Initial development work consisted of determining optimum process … more
Date: January 14, 1964
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Capsule irradiation of uranium with low alloy additions

Description: Here is a more complete description of the capsule test we discussed in our initial contact in December. I have included as much detailed description of the test as has been decided on to date. Also, there are some factors which, from previous similar test, I have found to be pertinent to the successful charging and irradiation performance of the capsules. There is one critical point that needs to be settled as soon as possible. In order to finish machining the outer diameter of the capsules, t… more
Date: January 16, 1964
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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Temperature calculations for a newly designed flexible HCR for the K Reactors

Description: The steadily increasing graphite stack distortion in the K Reactors has caused serious operating problems with the existing horizontal control rods. To compound the seriousness of the problems, the high level of reactor operation today and the anticipated higher level of operation in the future demands a reliable control rod system. A flexible control rod has been designed by Reactor Design, IPD, to facilitate reliable operation of the HCR system in spite of channel bowing arising from graphite… more
Date: January 27, 1964
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Report of invention: Increasing amounts of Pu-241 isotope

Description: This invention report suggests a method for drastically increasing the amount of Pu-241 in isotopic mixtures of plutonium. It is felt that with process experience, as much as 70 percent or more of the potential Pu-241 atoms can be concentrated in the fuel at one time. Such a concentration step would double the amount of production obtainable from Pu-241 by nuclear decay. The process to concentrate the Pu-241 consists of two basic steps: 1. Irradiate plutonium consisting largely of Pu-239 isotop… more
Date: January 28, 1964
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department
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Post-irradiation measurements of PT-546 fuel elements

Description: Early in December 1963 eighteen natural uranium columns were discharged from C Reactor. Fifteen (15) of these columns contained alternately charged HDS (test) and AlSi (control) fuel elements in the downstream half (positions 1--16); two columns were charged full length with HDS material; and one column was charged full length with AlSi material. All canned pieces were nominally C5NS dimensions except that the HDS pieces were slightly longer than the standard AlSi pieces. Uranium fabrication hi… more
Date: January 5, 1964
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Contribution to report ``Critical flow phenomena in two-phase mixtures and their relationships to reactor safety`` (for Geneva conference)

Description: Normally, in the flow of a flashing liquid through a pipe, it is assumed that the location of the choking phenomenon, if it exists, is at the exist of the pipe. Experiments have indicated that thee are circumstances under which choking can occur at the entrance instead. These experiments were performed to study the flashing of initially-compressed water through short lengths of pipe with length/diameter ratios of up to 20. Entrance configurations considered included sharp and rounded transition… more
Date: January 23, 1964
Creator: Zaloudek, F. R.
Partner: UNT Libraries Government Documents Department
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Production Test IP-580-AL: Irradiation of ``C`` and ``J`` fuel elements and thermocouple slugs for corrosion tests in the 1706-KE Single-Pass Facility

Description: The objective of the production test described in this report is to authorize the irradiation of aluminum-clad fuel elements with U{sup 235}-Al cores for corrosion testing in the 1706-KE Facility; the irradiation of thermocouple elements to measure the temperature of the aluminum cladding, installation of modified rear nozzles on the tubes in which these tests will be conducted., and the use of two regular KE tubes as controls. In order to measure corrosion at higher heat flux and surface tempe… more
Date: January 17, 1964
Creator: Dickinson, D. R. & Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Production test IP-543-A effluent sampling -- overbore tube. Final report

Description: It had been postulated that the increased film area of a charged overbore tube would be counterbalanced by the lower temperature fuel surface and decreased flux so that the radioisotope content of the effluent would be the same as that from a normal tube. In order to confirm or deny the postulate, Tube 3267-C was equipped with an effluent sample line under the provisions of PT-IP-543-A. Sampling and analytical work began in mid-April and continued through November, 1963. Effluent samples obtain… more
Date: January 9, 1964
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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A Single Stage Axial Compressor Blade Test Facility

Description: Abstract: This report gives a general description of the single stage axial compressor blade test facility located at the Oak Ridge Gaseous Diffusion Plant, Oak Ridge, Tennessee.
Date: January 13, 1964
Creator: Fee, G. G.
Partner: UNT Libraries Government Documents Department
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Effects of corrosion upon the adequacy of the 105-KE and 105-KW emergency coolant backup system

Description: When final system acceptance tests were performed on Project CGI-844, 100-K Coolant Backup System, it became evident that less than the design flow of 32,000 gpm was being achieved. Since the tests indicated that only 28,200 gpm was being supplied to KW and 26,700 gpm was being supplied to KE, it was obvious that the cross-tie lines had higher friction losses than anticipated. A study was therefore made to determine the effects of crosstie line cleaning to remove corrosion nodules. Calculations… more
Date: January 30, 1964
Creator: Watson, D. F.
Partner: UNT Libraries Government Documents Department
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Design criteria linear power rate-of-rise instrumentation

Description: Studies of reactor safety considerations have demonstrated the need for automatic safety circuit action based on the measured rate of power increase in the power level range from 10{sup {minus}2} to 10 {sup 0} times equilibrium power level. Budget and Preliminary Engineering Studies were performed. This document provides the design criteria for detailed design of the proposed Linear Power Rate-Of-Rise Instrumentation facilities and is applicable to any of the eight IPD reactors.
Date: January 16, 1964
Creator: Herrman, B. W.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: December 1963

Description: This report, for December 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Financial operations; facilities engineering; research; and employee relations. Weapons manufacturing operation; and safety and security.
Date: January 22, 1964
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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