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Hanford Operations Office monthly status and progress report. Part 1

Description: This is the monthly report for the Hanford Laboratories Operation, July, 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: July 1, 1960
Creator: Travis, J. E.
Partner: UNT Libraries Government Documents Department
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Welding Development Program: Resistance projection welding of Zircaloy-2 to natural uranium and resistance series seam welding of Zircaloy-2 to Zircaloy-2 to Zircaloy-2

Description: Discussions presented in this report result from product development activity conducted for the Hanford Atomic Products Operation of General Electric Company, Richland, Washington, by the Research Division, Sciaky Bros., Inc. Program objective, discussion of development effort, and test results are presented with a summary of final weld schedule, conclusions and recommendations. The objective of the development effort was to define the optimum projection weld area configuration and the weld sch… more
Date: November 1, 1960
Partner: UNT Libraries Government Documents Department
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Reactivity and efficiency trends vs operating trends for C, H, KE, and KW Reactors: 1955--1959

Description: Changes in operation and corresponding changes in the reactivity status of Hanford reactors are the result of a continuing effort to improve operating efficiency. Trends data related to these changes in operation and reactivity have been published previously for the periods from 1950 through 1958. The purpose of this report is to include trends data for 1959. All included data were selected from the sources listed as references on page 48. Bar graphs in the first part of the report show yearly … more
Date: June 1, 1960
Creator: Clark, D. E.
Partner: UNT Libraries Government Documents Department
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Design study interim report, RMA button line radiation reduction

Description: The design approach followed in this study is that of handling and processing plutonium solution and powders within tightly sealed but readily replaceable units of processing equipment, each one of which will do one step in the overall process. The presently used method is to use open equipment enclosed in glove boxes attached to a transporting device. Elimination of the glove box enclose and its replacement by tightly sealed and detachable equipment provides the accessability necessary for equ… more
Date: April 1, 1960
Creator: Kolb, J. W. & Bellarts, H. J.
Partner: UNT Libraries Government Documents Department
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Fuel element handling before irradiation

Description: This report on fuel element handling presents in some detail the current status of an engineering study which has been underway for some time, and which is continuing. The study was undertaken to determine if it is feasible, and if it is practicable, to revise the method and equipment used for fuel element handling with existing charging machines.
Date: February 1, 1960
Creator: Gilbert, R. D.
Partner: UNT Libraries Government Documents Department
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Proposal for the irradiation of cladding studies capsules

Description: In irradiations of rod cluster and tubular fuel elements and fuels rods in NaK-filled capsules, the Zircaloy-2 cladding has failed by necking in localized region. Purpose of the proposed tests to to help establish cladding thickness tolerances for NPR fuel elements, and to study the failure mechanism and influence of several variables.
Date: November 1, 1960
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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Appendix: Production Test IP-353-A, rapid depressurization of a KER loop

Description: Proposed fuel element loading and operating conditions for this test are tabulated. The loading is designed to provide high tube power and near-maximum-allowable coolant outlet temperature, accompanied by low fuel surface heat fluxes. Conditions which would exist during the proposed test were compared with those during the rapid depressurization incident in KER-2 on Jan. 31, 1960.
Date: September 1, 1960
Creator: Norwood, K. W.; Dulin, R. V.; Burns, W. A. & Dearing, F. E.
Partner: UNT Libraries Government Documents Department
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Note on effect of exposure on I & E fuel element rupture rate

Description: The rupture model presently being used by IPD Research and Engineering is the Weibull cumulative distribution function which in the region of interest, the model can be expressed approximately as: F(X) = failure rate in number of ruptures per total number of tubes, P = average tube power, T = average tube outlet temperature, M = exposure a{sub o}, a{sub 1}, a{sub 2}, a{sub 3} = parameters determined from rupture experience. F(X) = a{sub o}P{sup a1}T{sup a2}M{sub a3}. The parameters a{sub 1} = 3… more
Date: June 1, 1960
Creator: Spencer, H. G.
Partner: UNT Libraries Government Documents Department
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Increased pumping capacity at 181-D scope and justification

Description: The purpose of this report is to provide scope and justification for the installation of one new 900 HP pump in the 181-D Building and to tie the two 36-inch headers together in order to supply sufficient water to increase production at 105-D and 105-DR.
Date: June 1, 1960
Creator: Blanchette, V. G. & Brinkman, L. B.
Partner: UNT Libraries Government Documents Department
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Mechanical installation for standby power house, Building No. 184-N

Description: This specification covers the furnishing of piping, piping accessories, and certain specified mechanical equipment. Further it covers the provision of all labor, supervision, supplies, equipment and tools required for the handling, installation, painting, readying for operating and functional testing of all the equipment and systems described.
Date: September 1, 1960
Partner: UNT Libraries Government Documents Department
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Nuclear Battery-Thermocouple Type Summary Report

Description: The potential usefulness of approximately 1300 radioactive isotopes as a heat source for the thermoelectric generator was investigated. Only 47 were found to have the proper characteristics of high specific activity and usable haif-life combined with an easily absorbable radiation. These isotopes are discussed showing possible sources of supply, the hazards involved, and the expected performance. Three large Po/sup 210/ heat sources were designed and constructed (for battery use), including one… more
Date: October 1, 1960
Creator: Blanke, B. C.; Birden, J. H.; Jordan, K. C. & Murphy, E. L.
Partner: UNT Libraries Government Documents Department
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Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column

Description: Over-all mass transfer coefficients were determined independently of the interfacial area by considering the operation of the pulse column to be a stage- wise process. The calculated coefficients describe only the operation of the pulse column for the free rise of organic droplets through a stage, since in the downstroke the aqueous phase passes through the organic phase in the form of rivulets preferentially wetting the plates. The driving force for transfer was based on the aqueous phase conc… more
Date: November 1, 1960
Creator: Konopik, A. E. & Burkhart, L.
Partner: UNT Libraries Government Documents Department
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Determination of Aerodynamic Drag Parameters of Small Irregular Objects by Means of Drop Tests

Description: Drag coefficients were determined for various irregular objects such as glass fragments, stones, steel fragments, and spheres by means of drop tests for use in a mathematical model to correlate nuclear explosion blast experiments. Drop tests were also made on small laboratory animals and extrapolated to estimate the drag properties of man. A method was developed to estimate the average drag properties of man from his total surface area. (D.L.C.)
Date: June 1, 1960
Creator: Fletcher, E. R.; Albright, R. W.; Goldizen, V. C. & Bowen, I. G.
Partner: UNT Libraries Government Documents Department
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