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Hanford Laboratories Operation Monthly Activities Report: January 1961

Description: This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: February 15, 1961
Creator: Hanford Laboratories
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of production test IP-310-A-FP, determination of the dimensional stability of uranium fuel cores classified by the fuel core tester (UT-2)

Description: The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mix… more
Date: February 15, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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KW wet critical loading three group flux

Description: A calculation of the three-group flux distribution of the initial wet critical loading of KW reactor was made using the same calculation techniques as those employed in NPR three-group calculations. The calculation results are directly comparable to experimental data obtained during the KW loading. The calculated radial geometrical buckling of the critical loading is 48.2 {mu}b compared to a measured value of 49.8 {mu}b; these agree within estimated experimental error. The calculated reflector … more
Date: February 15, 1961
Creator: Simpson, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Artificial cooling of the Columbia River by dam regulation, 1960

Description: This report discusses benefits in an increase in the flow of water from the lower depths of the Grand Coulee Dam which was used to lower river temperature at HAPO. A net average daily reduction of over 1.2{degree}C resulted at HAPO with a peak of 2.7{degree}C. The Net Production gain from temperature change was 6910 MWD and the Cost of Control was: Grand Coulee Charges $3,120.00, and other (Estimated) 6,880.00 for a total of $10,00.00.
Date: February 15, 1961
Creator: Kramer, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: The evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam in a sodium-heated Type 316 stainless steel steam generator is reported. The purpose of the coating is to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It is concluded that the Kanigen coating does not afford adequate protection for the service conditions. (D.L.C.)
Date: February 15, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: January 1961

Description: This document details activities of the irradiation processing department during the month of January, 1961. 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; Employee Relations Operation; Financial Operation; and NPR Project.
Date: February 15, 1961
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, January 1961

Description: Modifications of EBWR are described, and data from analysis of control- rod operational crud deposit are tabulated. Development and construction progress on Borax V are summarized. Research for ZPR III is reported on a series of uranium oxide critical cores. Comparative data on composition, critical masses, and central fission ratios are tabulated for these assemblies. Developmental work on ZPR-VI, ZPR-IX, and Juggernaut is summarized, followed by a summary of EBR-I operation and development of… more
Date: February 15, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PATHFINDER ATOMIC POWER PLANT. HYDRAULIC ANALYSIS OF PATHFINDER BOILE. Summary Report

Description: A hydraulic analysis of the Pathfinder boiler core was completed. A description of flow paths including a schematic diagram is included. Pressure drops along primary and leakage fiow paths were calculatsd. After the resistance of each of the leakage paths was identified and the available driving forces in terms of pressure drops associated with the active fiow were established, the leakage rates were easily determined. The dependence of pressure drops on core operating parameters was investigat… more
Date: February 15, 1961
Creator: Sher, N.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility Study of a New Mass Flow System. Period Covered January 1- January 31, 1961

Description: Machining was completed on the s-tube flow element, and a spring, for use at a constant known temperature, was constructed for the flow element. Calculations for geometry factor, detector efficiency, and effective absorption along the useful radiation path were completed for the reed densitometer. The flow rate control was calibrated and performed satisfactorily. Response to step transient changes occurred with a damping constant of about 0.6 and an effective response time of 10 sec. Sources of… more
Date: February 15, 1961
Creator: Burgwald, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE PERMEATION OF HYDROGEN THROUGH HASTELLOY B

Description: The flux of hydrogen gas through Hastelloy B, hot forged to 20% reduction was determined as a function of membrane thickness, pressure differential, and temperature. The experimental data were fitted to the equation J = (1810 P/sup 1/2//X exp (-8422/T) where J is the flux (cc at STP/ (cm/sup 2/- hr)); P is the pressure (atmospheres); X is the membrane thickness (mm); and T is the temperature ( deg K). (auth)
Date: February 15, 1961
Creator: Rudd, D. W.; Vose, D. W. & Vetrano, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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KINETIC EXPERIMENTS ON WATER BOILERS. "A" CORE REPORT. PART V. CONTAINMENT ASPECTS OF PRESSURE WAVES FROM SOLUTION EXPANSION

Description: A theoretical treatment is made of the stress-strain and plastic flow properties of spherical shells of stainless steel under dynamic loading. The results are used to calculate the response of a homogeneous reactor core to inential pressure pulses. The importance of the duration of the pressure pulse as compared with a natural time or period of the material in plastic as well as in elastic deformation is noted. For a small homogeneous reactor core vessel, the natural plastic "swing time" is fou… more
Date: February 15, 1961
Creator: Greenfield, M.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design Modifications to the SRE During FY 1960

Description: The means used to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redssign of system components to utilize alteraate coolants such as nitrogen, air, and NaK. The use of kerosene to replace tetralin, where double containment is provided, is discussed. The physical properties are compared, and kerosene is shown to be free of the undesirable characteristics of tetralin. The fuelelement cleaning systsm was redesigned for steam w… more
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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