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  • Articles  (11)
  • tritium  (11)
  • 2020-2023
  • 1990-1994  (11)
  • Energy, Environment Protection, Nuclear Power Engineering  (11)
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  • Articles  (11)
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  • Energy, Environment Protection, Nuclear Power Engineering  (11)
  • 1
    ISSN: 1572-9591
    Keywords: tritium ; accident ; detonation ; deflagration
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Based on the existing conceptual design, a set of Reference Accident Sequences (RAS) has been defined by tritium system experts. This paper presents the main results related to a preliminary analysis of the following RAS for fuel cycle systems: hydrogen detonation in the isotopic separation system, rupture of a cryoline in a cryopump, fire in the long-term storage beds, and mechanical faulty operation in the pellet injector. The systems and the component mode of operation have been analyzed, as well as the characteristics of all streams, the inventory of T, D, and H, and the energy released under accident conditions. Failures that could give rise to the release of tritium and/or to the formation and ignition of oxygen/hydrogen mixtures and failures that could lead to containment pressure transients are discussed and examined.
    Type of Medium: Electronic Resource
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  • 2
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 12 (1993), S. 11-19 
    ISSN: 1572-9591
    Keywords: fusion reactor ; safety ; R&D task ; tritium ; activation products ; ITER
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract This paper aims at listing and evaluating the status of all the research and development (R&D) tasks necessary for the construction of a safe and environmentally benign fusion experimental reactor. At this time, it is not possible to define precisely the R&D tasks necessary for the licensing approval and those that are useful in improving safety but not necessarily required for licensing because the licensing procedure itself is still being discussed. Among the R&D tasks, the most important are considered to be those related to tritium safety, namely, those effective in reducing the uncertainty in tritium inventory in the plasma facing components and blanket, uncertainty in tritium permeation and leakage, and those to clarify tritium behavior in the containment and in the environment. The R&D tasks with second priority are judged to be those related to mobilization of the activation products such as activated erosion dust or the corrosion products. The volatilization of structural metal caused by the oxidation at high temperature seems to be highly unlikely but some experiments are needed to assure that this is the case.
    Type of Medium: Electronic Resource
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  • 3
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 9 (1990), S. 429-435 
    ISSN: 1572-9591
    Keywords: Deuteron ; Oppenheimer-Philiips reaction ; disintegration ; palladium ; neutron capture ; tritium ; cold fusion ; fissile isotopes
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract We discuss the Oppenheimer-Phillips process as a possible phenomenon leading to deuteron disintegration due to polarization in the Coulomb field of a target nucleus. This reaction may be possible in the context of electrochemically compressed deuterons in a palladium cathode. The process is exothermic and may lead to neutron capture from the deuterons into the palladium isotopes, as well as between the deuterons themselves. In the last case, the equivalent of the proton branch of the D-D fusion reaction occurs in preference to the neutron branch. Such a process could provide a model for the processes involved in the observed energy release and tritium production in conjunction with neutron suppression in recent experiments. Possible interactions with Be and fertile isotopes are discussed in the context of breeding fissile isotopes in subcritical configurations.
    Type of Medium: Electronic Resource
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  • 4
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 9 (1990), S. 483-485 
    ISSN: 1572-9591
    Keywords: Fusion ; branching ; tritium ; deuterium ; neutrons
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The major reaction products that have been possibly associated with cold fusion reactions are neutrons, protons, tritium, He-3, He-4, internal conversion electrons, and gamma radiation. The branching ratios and relative reaction rates for these products are examined for consistency with cold fusion experiments. Both theoretical calculations and experimental data are examined and presented. The He-4 plus internal conversion reaction has been proposed to explain the absence of neutrons or gamma rays in successful cold fusion experiments. However, this reaction is not favored, even in a deuterium-palladium system. Measurement of these reactions must be made carefully owing to the presence in the background of 2.2-MeV gamma rays, background tritium in heavy water, and neutrons from the photodisintegration of the deuterium from background radiation. These problems confronting cold fusion experiments are addressed.
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  • 5
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 12 (1993), S. 149-156 
    ISSN: 1572-9591
    Keywords: environment ; tritium ; activation products ; dose calculations ; NET, ITER
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract In view of public acceptance and the licensing procedure of projected fusion reactors, the release of tritium and activation products during normal operation as well as after accidents is a significant safety aspect. Calculations have been performed under accidental conditions for unit releases of corrosion products from water coolant loops, of first wall erosion products including different coating materials, and of tritium in its chemical form of tritiated water (HTO). Dose assessments during normal operation have been performed for corrosion products from first wall primary coolant loop and for tritium in both chemical forms (HT/HTO). The two accident consequence assessment (ACA) codes UFOTRI and COSYMA have been applied for the deterministic dose calculations with nearly the same input variables and for several radiological source terms. Furthermore, COSYMA and NORMTRI have been applied for routine release scenarios. The paper analyzes the radioation doses to individuals and the population resulting from the different materials assumed to be released in the environment.
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  • 6
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 12 (1993), S. 35-40 
    ISSN: 1572-9591
    Keywords: tritium ; graphite ; tokamak ; DIII-D
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The amount of tritium in the carbon tiles used as a first wall in the DIII-D tokamak was measured recently when the tiles were removed and cleaned. The measurements were made as part of the task of developing the appropriate safety procedures for processing of the tiles. The surface tritium concentration on the carbon tiles was surveyed and the total tritium released from tiles samples was measured in test bakes. The total tritium in all the carbon tiles at the time the tiles were removed for cleaning is estimated to be 15 mCi and the fraction of tritium retained in the tiles from DIII-D operations has a lower bound of 10%. The tritium was found to be concentrated in a narrow surface layer on the plasma facing side of the tile, was fully released when baked to 1000°C, and was released in the form of tritiated gas (DT) as opposed to tritiated water (DTO) when baked.
    Type of Medium: Electronic Resource
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  • 7
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 9 (1990), S. 351-354 
    ISSN: 1572-9591
    Keywords: Pons ; Fleischmann ; electrolysis ; electrolyte ; neutrons ; tritium
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Although major controversy still remains as to the source of the excess thermal power output reported from diverse successful cold fusion calorimetry experiments, considerable independent evidence does exist that low-level, deuterium fueled, cold fusion reactions can occur based upon reported neutron and tritium measurements. Because the specific fusion power output may be very low in present cold fusion experiments, there are numerous features and conditions associated with cold fusion experiments which might enhance fusion reaction rates. The principal focus of attention in enhancing cold fusion reactions occurring in an electrolytic cell is the palladium cathode where deuterium is preferentially absorbed into the cathode. The cathode's physical, metallurgical, and chemical characteristics such as purity, lattice cell size and orientation, chemical and hydrodynamic properties, and its electrical surface conditions and prevailing reactions are known to be important for maximizing deuterium loading. Even the geometrical size and configuration of the cathode and the crystalline grain size and conditioning are apparently important. The composition, pH, flow of the electrolyte, electrolysis employing rapidly time varying electrical potential and current and very high pressure and low temperature operation may also enhance fusion reaction rates.
    Type of Medium: Electronic Resource
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  • 8
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 12 (1993), S. 115-119 
    ISSN: 1572-9591
    Keywords: tritium ; implantation ; experiments ; safety ; ITER
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The Tritium Plasma Experiment was assembled at Sandia National Laboratories, Livermore and is being moved to the Tritium Systems Test Assembly facility at Los Alamos National Laboratory to investigate interactions between dense plasmas at low energies and plasma-facing component materials. This apparatus has the unique capabilty of replicating plasma conditions in a tokamak divertor with particle flux densities of 2 × 1023 ions/m2.s and a plasma temperature of about 15 eV using a plasma that includes tritium. An experimental program has been initiated using the Tritium Plasma Experiment to examine safety issues related to tritium in plasma-facing components, particularly the ITER divertor. Those issues include tritium retention and release characteristics, tritium permeation rates and transient times to coolant streams, surface modification and erosion by the plasma, the effects of thermal loads and cycling, and particulate production. An industrial consortium led by McDonnell Douglas will design and fabricate the test fixtures.
    Type of Medium: Electronic Resource
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  • 9
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 12 (1993), S. 145-148 
    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).
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  • 10
    ISSN: 1572-9591
    Keywords: tritium ; emission ; radiation dose ; review
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A review of technology assessment studies as well as original research papers is presented in two diagrams with respect to estimating (1) the performance of fusion reactors in containing tritium, and (2) the radiological consequences of normal operational losses as well as accidental releases of tritium. Predictions are shown to vary over several orders of magnitude.
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