IEEE Transactions on Nuclear Science

Issue 1 • Feb. 1968

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Displaying Results 1 - 25 of 79
  • [Front cover]

    Publication Year: 1968, Page(s): c1
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  • IEEE Nuclear Science Group

    Publication Year: 1968, Page(s): c2
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  • Table of contents

    Publication Year: 1968, Page(s):1 - 4
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  • Session Chairmen

    Publication Year: 1968, Page(s):5 - 6
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  • The Nucleus

    Publication Year: 1968, Page(s):7 - 8
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  • A Gamma Compensated Neutron Ionization Chamber Detector for the Nerva Reactor

    Publication Year: 1968, Page(s):9 - 14
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (961 KB)

    A compensated ionization chamber, the WX-5362, has been developed for use in the NERVA program as a neutron flux detector for reactor control. The chamber has been designed to withstand the extremes of radiation, temperature, shock and vibration associated with the NERVA reactor. View full abstract»

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  • Gamma Discrimination and Sensitivities of Averaging and RMS Type Detector Circuits for Campbelling Channels

    Publication Year: 1968, Page(s):15 - 21
    Cited by:  Papers (4)  |  Patents (2)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (1725 KB)

    Experiments are described in which the performance of a linear type detector circuit is compared with a mean square type detector circuit for Campbell measurements. The need for pulse overlap is demonstrated for the linear type detector which requires a minimum angular cutoff frequency, #x003C9;L, equal to the lowest desired pulse rate. Measurements with the two types of detector circuits in a hig... View full abstract»

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  • The Performance of a Counting-Mean-Square Voltage Channel in the EBR-II

    Publication Year: 1968, Page(s):22 - 27
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    A wide range neutron flux monitoring test channel based on counting and mean-square voltage techniques has been installed at the EBR-II. The measured responses to neutron flux are presented and compared to those predicted. Data taken while the reactor is on an essentially constant period during typical re-starts are shown. The gamma discrimination ratio for this system has been determined and is d... View full abstract»

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  • Summary of an Analysis of the Eddy-Current Flowmeter

    Publication Year: 1968, Page(s):28 - 36
    Cited by:  Papers (9)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (999 KB)

    The eddy-current flowmeter seems well adapted to measurements in high-temperature liquid-metal systems, where deterioration of the properties of permanent magnets and other ferromagnetic parts or bearing problems may seriously degrade the performance of other types. It is shown analytically that velocity-profile errors and temperature errors can be minimized by selecting a suitable operating frequ... View full abstract»

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  • The Calibration and Stability of a 1200°F Permanent Magnet In-Core Sodium Flowmeter

    Publication Year: 1968, Page(s):37 - 40
    Cited by:  Papers (1)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (1131 KB)

    A previously described, permanent magnet (PM), in-core flowmeter for use in sodium cooled reactors has been fabricated and installed in the Argonne National Laboratory (ANL) Sodium Flowmeter Calibration Loop. The calibration test facility and procedures are described and a typical family of flowmeter calibration curves are presented. The measured sensitivity is compared to that theoretically predi... View full abstract»

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  • A Dewpoint Device for HTGR Coolant

    Publication Year: 1968, Page(s):41 - 45
    Cited by:  Papers (1)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (1401 KB)

    High-temperature gas-cooled reactors (HTGRs) use a gaseous coolant for heat transfer between the nuclear core and two or more steam generators. Leakage of steam or water from the steam generators to the coolant would expose the nuclear core to water vapor. A moisture measuring system is required to determine the moisture content of the coolant gas in the range of 0.1 to 3000 volume parts per milli... View full abstract»

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  • Measurement of Shutdown Margin

    Publication Year: 1968, Page(s):46 - 56
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (1443 KB)

    A method was developed and investigated for directly measuring the shutdown margin in a reactor operating at a subcritical steady state. Measurements were made on the Iowa State University UTR-10 reactor with conditions ranging from almost critical to fully shutdown. The method is based on the fact that the frequency dependent transfer function of the reactor is a measure of the response of the re... View full abstract»

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  • A Direct and Nonlinear Programming Approach to the Optimal Nuclear Reactor Shutdown Control

    Publication Year: 1968, Page(s):57 - 59
    Cited by:  Papers (4)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (497 KB)

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  • Optimization of Nuclear Reactor Fuel Recycle via Linear and Quadratic Programming

    Publication Year: 1968, Page(s):60 - 64
    Cited by:  Papers (14)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (712 KB)

    The possibility of applying Linear or Quadratic Programming to the problem of optimizing nuclear reactor fuel recycle, is investigated. It is demonstrated, that the methods mentioned, may be applied successfully to a simplified model of a nuclear reactor. An appropriate representation of the fuel recycle as a feedback control system is proposed. An iterative algorithm to establish the refueling ti... View full abstract»

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  • Computation of Optimal Controls for a Nuclear Rocket Reactor

    Publication Year: 1968, Page(s):65 - 73
    Cited by:  Papers (1)
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  • Inherent Control of Nuclear Propulsion Reactors

    Publication Year: 1968, Page(s):74 - 76
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    Recent developments in the control of nuclear propulsion reactors are discussed. Analog simulation studies of engine performance have emphasized: (1) the use of hydrogen propellant moderating qualities for reactor power control, instead of neutron absorption in the control drums, and (2) the use of reactor temperature as the power reference, instead of neutron density. The concept of inherent cont... View full abstract»

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  • Extended Capability for Fast Neutron Hodoscope Used at Treat

    Publication Year: 1968, Page(s):77 - 86
    Cited by:  Papers (6)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (3210 KB)

    The fast neutron hodoscope used at TREAT reactor for fuel meltdown studies has been improved to permit count rates above 106/sec in each channel. Also a digital readout system, based on integrated circuit scalers, has been introduced. Peak instantaneous data rate capability, now about 107/sec, can be expanded to 109/sec. View full abstract»

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  • Digital Computer Control of a Research Reactor

    Publication Year: 1968, Page(s):87 - 92
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (1970 KB)

    This report describes a feasibility experiment for a fully automatic operation of Hitachi Training Reactor, emploving an digital computer control system. The system consists of a small control computer (2K words), an input-output peripherals, 3 BF3 counters and a countrol rod mechanism driven by a pulse motor. View full abstract»

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  • Programs and Systems for On-Line Computers in Low Energy Nuclear Physics

    Publication Year: 1968, Page(s):93 - 102
    Cited by:  Papers (3)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (1652 KB)

    A conference held five years ago this month served, among other things, to introduce the notion to a substantial representation from the community of experimental nuclear physicists that a stored program computer could be used as a powerful, flexible tool for extending the scope of, as well as for aiding in the detailed execution of their experimental programs. The appreciation of the possibilitie... View full abstract»

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  • A Data Link between Small Computers and a CDC 6600

    Publication Year: 1968, Page(s):103 - 108
    Cited by:  Patents (1)
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    At Lawrence Radiation Laboratory small computers are used on-line with high-energy physics experiments. When the experimenter desires to estimate the relative value of the experimental data, the necessary analysis can only be performed on a large computer. Hence, the need arose for a fast two-way Data Link between one or more small computers and a large computer. The lack of interrupt facilities i... View full abstract»

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  • Programming for an Advanced Nuclear Phiysics Data Acouisition System

    Publication Year: 1968, Page(s):109 - 116
    Cited by:  Papers (3)
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    Experience in the design and operation of a previously reported (1) hardware-software computer-based on-line nxuclear physics data acquisition system is described. Major emphasis is placed upon the structure of the programming system, which embodies data acquisition, display, control,, and analysis facilities, and a supervisor capable of coordinating the parallel operation of multiple tasks. Basic... View full abstract»

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  • Counting Schemes for Nuclear Data Acquisition on Small Computers

    Publication Year: 1968, Page(s):117 - 122
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    In using a small computer for accumulating a pulse height spectrum, it is often the case that the word length is too small to store the counts on a one-word-per-channel basis. The use of double precision to avoid this problem is wasteful of storage space. One way to avoid this waste is to store the differences between counts in two adjacent channels rather than the counts themselves. This can be a... View full abstract»

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  • The On-Line Application of Electronic Calculators to Nuclear Counting Systems

    Publication Year: 1968, Page(s):123 - 128
    Cited by:  Papers (1)
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (2284 KB)

    The Los Alamos Scientific Laboratory, operated by the University of California for the U. S. Atomic Energy Commission, continues to be active in developing, designing, and building nuclear reactors. The Nondestructive Testing Group has been instrumental in the support of these programs by providing services in the inspection of the reactor components. Nuclear counting systems are applied in many p... View full abstract»

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  • NSRL On-Line Computer System

    Publication Year: 1968, Page(s):129 - 134
    Cited by:  Papers (2)
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  • On-Line Data Collection by Computer in a Multi-Experiment Biomedical Gamma Spectroscopy System

    Publication Year: 1968, Page(s):135 - 137
    Request permission for commercial reuse | Click to expandAbstract |PDF file iconPDF (456 KB)

    A system is described in which a PDP-8 computer collects data on-line from up to twenty high-resolution pulse height analyzers used in biomedical gamma spectroscopy counting. The computer takes data directly from the analog-to-digital converters and stores it unsorted on IBM magnetic tape. These tapes are sorted and analyzed off-line on larger computers. An oscilloscope provides two modes of displ... View full abstract»

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Aims & Scope

IEEE Transactions on Nuclear Science focuses on all aspects of the theory and applications of nuclear science and engineering, including instrumentation for the detection and measurement of ionizing radiation; particle accelerators and their controls; nuclear medicine and its application; effects of radiation on materials, components, and systems; reactor instrumentation and controls; and measurement of radiation in space.

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