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  • 1
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    An investigation of energy balances in palladium cathode electrolysis experiments (1990)
    Springer
    Details
    Publication Date: 1990-09-01
    Print ISSN: 0164-0313
    Electronic ISSN: 1572-9591
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Published by Springer
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    PAPER CURRENT
  • 2
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    Tritium environmental transport studies at TFTR (1993)
    Springer
    Details
    Publication Date: 1993-06-01
    Print ISSN: 0164-0313
    Electronic ISSN: 1572-9591
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Published by Springer
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    PAPER CURRENT
  • 3
    Electronic Resource
    Electronic Resource
    Implanted Deuterium Retention and Release in Carbon-Coated Beryllium (1997)
    Springer
    Journal of fusion energy 16 (1997), S. 95-100 
    Details
    ISSN: 1572-9591
    Keywords: Fusion ; beryllium ; tritium ; coatings ; mobilization ; experiments
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Deuterium implantation experiments have been conducted on samples of clean and carbon-coated beryllium. These studies entailed preparation and characterization of beryllium samples coated with carbon thicknesses of 100, 500, and 1000 Å. Heat treatment of a beryllium sample coated with carbon to a thickness of approximately 100 Å revealed that exposure to a temperature of 400°C under high vacuum conditions was sufficient to cause substantial diffusion of beryllium through the carbon layer, resulting in more beryllium than carbon at the surface. Comparable concentrations of carbon and beryllium were observed in the bulk of the coating layer. Higher than expected oxygen levels were observed throughout the coating layer as well. Samples were exposed to deuterium implantation followed by thermal desorption without exposure to air. Differences were observed in deuterium retention and postimplantation release behavior in the carbon-coated samples as compared with bare samples. For comparable implantation conditions (sample temperature of 400°C and an incident deuterium flux of approximately 6 × 1019 D/m2-s), the quantity of deuterium retained in the bare sample was less than that retained in the carbon-coated samples. Further, the release of the deuterium took place at lower temperatures for the bare beryllium surfaces than for carbon-coated beryllium samples.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1023/A:1022569130666
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    Paper (German National Licenses)
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  • 4
    Electronic Resource
    Electronic Resource
    An investigation of energy balances in palladium cathode electrolysis experiments (1990)
    Springer
    Journal of fusion energy 9 (1990), S. 337-343 
    Details
    ISSN: 1572-9591
    Keywords: Cold fusion ; energy balance
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A series of experiments was performed at the Idaho National Engineering Laboratory (INEL) to investigate mechanisms that may contribute to energy flows in electrolysis cells like those of Fleischmann and Pons. Ordinary water (H2O), heavy water (D2O), and a mixture of the two were used in the INEL experiments. Cathodes used include a 51-μm Pd foil and 1-mm diameter extruded wire Pd rods in straight and coiled configurations. Energy balances in these experiments revealed no significant net gain or net loss of energy. Cell overpotential curves were fit well with a Tafel equation, with parameters dependent on electrode configuration, electrolyte composition, and temperature. Water evaporation and interactions of hydrogen isotopes with the Pd cathode were evaluated and found not to be significant to energy balances. No ionizing radiation, tritium production, or other evidence of fusion reactions was observed in the INEL experiments.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF01059253
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  • 5
    Electronic Resource
    Electronic Resource
    An Overview of INEL Fusion Safety R&D Facilities (1997)
    Springer
    Journal of fusion energy 16 (1997), S. 113-118 
    Details
    ISSN: 1572-9591
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen generation rates and tritium mobilization rates in high-temperature (up to 1200°C) fusion relevant materials exposed to steam. The Volatilization of Activation Product Oxides Reactor Facility provides information on mobilization and transport and chemical reactivity of fusion relevant materials at high temperature (up to 1200°C) in an oxidizing environment (air or steam). The Fusion Aerosol Source Test Facility is a scaled-up version of VAPOR. The ion-implanta-tion/thermal-desorption system is dedicated to research into processes and phenomena associated with the interaction of hydrogen isotopes with fusion materials. In this paper we describe the capabilities of these facilities.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1023/A:1022525315645
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  • 6
    Electronic Resource
    Electronic Resource
    Tritium environmental transport studies at TFTR (1993)
    Springer
    Journal of fusion energy 12 (1993), S. 145-148 
    Details
    ISSN: 1572-9591
    Keywords: tritium ; transport ; monitoring ; environment ; model ; validation
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Environmental tritium concentrations will be measured near the Tokamak Fusion Test Reactor (TFTR) to help validate dynamic models of tritium transport in the environment. For model validation the database must contain sequential measurements of tritium concentrations in key environmental compartments. Since complete containment of tritium is an operational goal, the supplementary monitoring program should be able to glean useful data from an unscheduled acute release. Portable air samplers will be used to take samples automatically every 4 hours for a week after an acute release, thus obtaining the time resolution needed for code validation. Samples of soil, vegetation, and foodstuffs will be gathered daily at the same locations as the active air monitors. The database may help validate the plant/soil/air part of tritium transport models and enhance environmental tritium transport understanding for the International Thermonuclear Experimental Reactor (ITER).
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF01059370
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