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A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction

Description: Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations.
Date: April 1966
Creator: Koppel, L. B.; Alfredson, P. G.; Anastasia, L. J.; Knudsen, I. E. & Vogel, G. J.
Partner: UNT Libraries Government Documents Department
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Television System Study for Accident Recovery : Phase I

Description: From abstract: "A previous study of equipment necessary for clean-up following a nuclear accident indicated a need for a portable television system capable of operating in hazardous environments during recovery operations. A system to accomplish this is described and justified in this study."
Date: April 1966
Creator: Talpis, N. A. & Burge, D. L.
Partner: UNT Libraries Government Documents Department
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1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description

Description: From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
Date: April 1967
Creator: Boyer, R. L.
Partner: UNT Libraries Government Documents Department
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1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1

Description: From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
Date: June 1967
Creator: Goulding, B. J.
Partner: UNT Libraries Government Documents Department
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A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments

Description: Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and … more
Date: September 1967
Creator: Bryant, Lawrence T.; Amiot, Lawrence W.; Dickerman, Charles E. & Stephany, William P.
Partner: UNT Libraries Government Documents Department
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Design and Testing of a High-Heat Flux Electron-Bombardment Heater

Description: Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.
Date: March 1968
Creator: Carlson, R. D. & Holtz, R. E.
Partner: UNT Libraries Government Documents Department
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FUDGE 4A: A Computer Program for Gamma Dose Rate Distribution from Rectangular Sources

Description: Report issued by the Brookhaven National Laboratory discussing the recently modified FUDGE 4A computer program. As stated in the introduction, "this report presents the details and technical information required for the proper use of FUDGE 4A" (p. 1). This report includes tables, and illustrations.
Date: August 1968
Creator: Galanter, Leonard & Krishnamurthy, Krishnaswamy
Partner: UNT Libraries Government Documents Department
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Nuclear Power and Water Desalting Plants for Southwest United States and Northwest Mexico: A Preliminary Assessment

Description: From introduction: Preliminary assessment between the United States, Mexico, and the IAEA on the technical and economic practicability of a dual-purpose nuclear power plant designed to produce fresh water and electricity for the southern border portion of the Colorado River.
Date: September 1968
Partner: UNT Libraries Government Documents Department
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Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

Description: From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
Partner: UNT Libraries Government Documents Department
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Structure, Function, and Evolution in Proteins: Report of Symposium held June 3-5, 1968, Volume 1

Description: Report issued by the Brookhaven National Laboratory containing conference proceedings from the first three sessions of the Symposium in Biology, held June 3-5, 1968. It includes research and papers discussing developments in the structure, function, and evolution in proteins with tables, illustrations, and photographs.
Date: February 1969
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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