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  • Articles  (6)
  • neutron source  (6)
  • 1985-1989  (6)
  • 1965-1969
  • 1989  (6)
  • Energy, Environment Protection, Nuclear Power Engineering  (6)
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  • Articles  (6)
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  • 1985-1989  (6)
  • 1965-1969
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Topic
  • Energy, Environment Protection, Nuclear Power Engineering  (6)
  • 1
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 8 (1989), S. 147-155 
    ISSN: 1572-9591
    Keywords: neutron source ; fusion materials ; radiation damage ; transmutation products
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The construction and operation of an intense 14-MeV neutron source is essential for the development and eventual qualification of structural materials for a fusion reactor demonstration plant (DEMO). Because of the time required for materials development and the scale-up of materials to commercial production, a decision to build a neutron source should precede engineering design activities for a DEMO by at least 20 years. The characteristic features of 14-MeV neutron damage are summarized including effects related to cascade structure, transmutation production, and dose rate. The importance of a 14-MeV neutron source for addressing fundamental radiation damage issues, alloy development activities, and the development of an engineering database is discussed. For these considerations, the basic requirements and machine parameters are derived.
    Type of Medium: Electronic Resource
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  • 2
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 8 (1989), S. 169-180 
    ISSN: 1572-9591
    Keywords: neutron source ; neutron production ; spallation targets
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The paper outlines the physics of the spallation reaction and the resulting rules of thumb with respect to neutron yield, heat deposition, and energy distribution. Technical problems and performance expectations are discussed on the basis of two high beam power spallation neutron source projects, namely, the German SNQ Project (not funded) and the Swiss SINQ Project (under construction). Since both of these projects were designed mainly for thermal neutron scattering application, emphasizing the production of a high flux of moderated neutrons, an alternative conceptual design is presented which, while still allowing the extraction of cold and thermal neutron beams, also offers the opportunity of placing samples into positions where the neutron spectrum has changed only very little due to transport in matter. The anisotropy of the high-energy neutron field can be taken advantage of to select, to some extent, how much of the high energy component will be seen by the specimens. No technical design concept exists so far for a spallation neutron source for fusion materials test purposes, and more detailed studies would be required to assess its value and usefulness. However, a source for combined use for different purposes seems to be feasible without too many compromises.
    Type of Medium: Electronic Resource
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  • 3
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 8 (1989), S. 181-192 
    ISSN: 1572-9591
    Keywords: Spallation ; liquid target ; proton accelerator ; neutron source ; high energy ; fusion technology ; material damage ; EOL experiments ; atomic displacement ; transmutant production ; cold neutron
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Spallation reactions are a very important option for efficient neutron sources appropriate for fusion materials testing. An “option of this option” is the EURAC concept, which makes use of short-term accelerator technology in the cheapest way and is proved to provide the needed neutron flux to verify fast experiments on fusion materials performance. Its flexible conception allows an optimum combination of very high fluxes of about 1016 n/cm2/s, with decreasing fluxes along the testing zones in enough volume to perform the correct irradiations. With this assumption, the rate effect can be perfectly analyzed together with the end-of-life conditions assumed in the structural material of the future fusion environments. The possible negative effects of the high-energy neutrons in the Spallation spectrum have been taken into account, concluding their non-significance in the desired damage parameters. The EURAC concept can also be considered in light of other purposes like incineration processes,μ production, and, with the appropriate booster, high-flux cold neutron source.
    Type of Medium: Electronic Resource
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  • 4
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 8 (1989), S. 249-268 
    ISSN: 1572-9591
    Keywords: Fusion ; reversed-field pinch ; neutron source ; nuclear technology
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The conceptual design of an ohmically heated, reversed-field pinch (RFP) operating at ∼5-MW/m2 steady-state DT fusion neutron wall loading and ∼124-MW total fusion power is presented. These results are useful in projecting the development of a cost effective, low-input-power (∼206 MW) source of DT neutrons for large-volume (∼10 m3), high-fluence (3.4 MW yr/m2) fusion nuclear materials and technology testing.
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  • 5
    ISSN: 1572-9591
    Keywords: Fusion materials ; materials development ; neutron damage ; neutron source
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The design and performance of a relatively low-cost, plasma-based, 14-MeV D-T neutron source for accelerated end-of-life testing of fusion reactor materials are described in this article. An intense flux (up to 5×1018 n/m2·s) of 14-MeV neutrons is produced in a fully-ionized high-density tritium target (n e ≈ 3×1021 m−3) by injecting a current of 150-keV deuterium atoms. The tritium plasma target and the energetic D+ density produced by D0 injection are confined in a column of diameter ⩽ 0.16 m by a linear magnet set, which provides magnetic fields up to 12 T. Energy deposited by transverse injection of neutral beams at the midpoint of the column is conducted along the plasma column to the end regions. Longitudinal plasma pressure in the column is balanced by neutral gas pressure in the end tanks. The target plasma temperature is about 200 eV at the beam-injection position and falls to 5 eV or less in the end region. Ions reach the walls with energies below the sputtering threshold, and the wall temperature is maintained below 740 K by conventional cooling technology.
    Type of Medium: Electronic Resource
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  • 6
    ISSN: 1572-9591
    Keywords: fusion ; dense Z-pinch ; neutron source ; nuclear technology
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The dense Z-pinch (DZP) is one of the earliest and simplest plasma heating and confinement schemes. Recent experimental advances based on plasma initiation from hair-like (10s μm in radius) solid hydrogen filaments have so far not encountered the usually devastating MHD instabilities that plagued early DZP experimenters. These encouraging results along with the debut of a number of proof-of principle, high-current (1–2 MA in 10–100 ns) experiments have prompted consideration of the DZP as a pulsed source of DT fusion neutrons of sufficient strength (S N ⩾ 1019 n/s) to provide uncollided neutron fluxes in excess ofI w = 5–10 MW/m2 over test volumes of 10–30 liters or greater. While this neutron source would be pulsed (100s ns pulse widths, 10–100 Hz pulse rate), giving flux time compressions in the range 105–106, its simplicity, near-term feasibility, low cost, high-Q operation, and relevance to fusion systems thatmay provide a pulsed commercial end-product, e.g., inertial confinement or the DZP itself, together create the impetus for preliminary consideration as a neutron source for fusion nuclear technology and materials testings. The results of a preliminary parametric systems study (focusing primarily on physics issues), conceptual design, and cost vs. performance analyses are presented. The DZP promises an inexpensive and efficient means to provide pulsed DT neutrons at an average rate in excess of 1019 n/s, with neutron currents Iw≲10 MW/m2 over volumes Vexp ⩾ 30 liter using single-pulse technologies that differ little from those being used in present-day experiments.
    Type of Medium: Electronic Resource
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