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FFTF FUELS DEVELOPMENT CURRENT PRELIMINARY DATA REPORT FOR MAY 1969

Description: This document comprises a compilation of preliminary data generated during the reporting month of May, 1969. The data relate to fuel element development, fuels quality assurance, cladding development, fuels evaluation, and offsite fuel programs.
Date: May 31, 1969
Partner: UNT Libraries Government Documents Department
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Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
Partner: UNT Libraries Government Documents Department
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Quarterly Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Quarterly report with the objectives of evaluating, producing, and maintaining of an up-to-dat set of basic nuclear data; producing and evaluating of multigroup constants; and the improvement of present day methods of neutronic calculations as relates to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
Partner: UNT Libraries Government Documents Department
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Rumania's Reaction to the Soviet Intervention in Czechoslovakia

Description: This report describes Rumania's (Romania's) history as a Communist nation under the Soviet Union, as well as Rumania's reaction to the Soviet Union intervening in Czechoslovakia in 1968.
Date: May 23, 1969
Creator: Sarkissian, Arshag O.
Partner: UNT Libraries Government Documents Department
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First FFTF local clad temperature tests with 7-pin bundles

Description: A series of three tests will be performed to evaluate: temperature gradients between wall and central coolant channels in an FFTF fuel assembly to assess thermal stress level in the pins. The potential hot spot caused by the presence of a wire wrap spacer. A single electrically-heated 7-pin fuel assembly model will be used to perform these tests. The configuration is summarized in Table 1 and the instrumentation in Figure 1. Pins 1, 2, and 7, along with the local coolant thermocouples, characte… more
Date: May 20, 1969
Creator: Yatabe, J. M.; Collingham, R. E.; Hill, J. R. & Thorne, W. L.
Partner: UNT Libraries Government Documents Department
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Sensitivity Training in the 1960's: Selected References

Description: This report lists sources explaining the experimentally based learning method and describing its application in a number of fields.
Date: May 20, 1969
Creator: Loo, Shirley
Partner: UNT Libraries Government Documents Department
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Douglas United Nuclear monthly report, April 1969

Description: This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of April 1969.
Date: May 16, 1969
Partner: UNT Libraries Government Documents Department
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FFTF FUEL PIN AND SUBASSEMBLY CONCEPTUAL DESIGN METHODS AND DATA

Description: The major technical bases for the FFTF first core fuel assembly conceptual design are presented in four general categories: (1) thermal, (2) hydraulic, (3) structural and (4) performance-manufacturing design characteristics. Recommended design values and conceptual engineering drawings of the fuel pin and subassembly are included .
Date: May 15, 1969
Creator: Stevens, E. G.; Cohn, P. D.; Jackson, R. J.; Kolesar, D. C,; Mohr, C. L.; Padilla, A. et al.
Partner: UNT Libraries Government Documents Department
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HEAT LOAD ON VESSEL WALL COOLANT STREAM

Description: The FTR vessel wall will be cooled with inlet primary coolant which bypasses the core and flows through an annulus formed by the vessel wall and the thermal barrier. heat transfer to the by-pass coolant stream is by raial conduction from the surrounding sodium pool through the thermal barrier wall. In the analysis, the temperature rise of the by-pass coolant stream was derived as a function of the wall thickness of the thermal barrier and the flow rate of the by-pass stream.
Date: May 15, 1969
Creator: Muraoka, John
Partner: UNT Libraries Government Documents Department
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NUMBER AND TYPE OF OPERATING CYCLES FOR THE FFTF

Description: The choice of materials and other vessel design decisions necessary to provide the desired life expectancy for the FTR vessel are partially dependent upon estimates of the number and type of reactor shutdowns and startups which may be anticipated. Current estimates of these so-called "cycles" are given, including scram frequency, experimental outage frequency, standard shutdowns and startups, and rapid controlled shutdowns. Also discussed are abnormal heatup or cooldown, and tentative… more
Date: May 15, 1969
Creator: Boyd, D. C.
Partner: UNT Libraries Government Documents Department
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SNAP-23A Program. Phase I. Thermoelectric Converter Development Program. Monthly report, April 1969

Description: The following activities were conducted during the month of April 1969: continued effort toward completion of the detailed design of the PMC-2 converter, conducted technical liaison with Westinghouse with respect to the power cable specification, conducted potting test for evaluation of material suitable for SNAP-23A converter PMC-2 leak specification, and completed design of parts for the Weld Development Program. Test data evaluation and analysis were performed on the following long-term test… more
Date: May 15, 1969
Partner: UNT Libraries Government Documents Department
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The fees and incomes of physicians

Description: This report presents The fees and incomes of physicians according to the public and congressional interest.
Date: May 8, 1969
Creator: Markus, Glenn R.
Partner: UNT Libraries Government Documents Department
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