• DocumentCode
    2045212
  • Title

    A 14-MeV beam-plasma neutron source for materials testing

  • Author

    Futch, A.H. ; Coensgen, F.H. ; Damm, C.C. ; Molvik, A.W.

  • Author_Institution
    Lawrence Livermore Nat. Lab., CA, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    666
  • Abstract
    The design and performance of 14-MeV beam-plasma neutron sources for accelerated testing of fusion reactor materials are described. Continuous production of 14-MeV neutron fluxes in the range of 5 to 10 MW/m2 at the plasma surface are produced by D-T reactions in a two-component plasma. In the current designs, 14-MeV neutrons result from collisions of energetic deuterium ions created by transverse injection to 150-keV deuterium atoms on a fully ionized tritium target plasma. The beam energy, which is deposited at the center of the tritium column, is transferred to the warm plasma by electron drag, which flows axially to the end regions. Neutral gas at high pressure absorbs the energy in the tritium plasma and transfers the heat to the walls of the vacuum vessel. The plasma parameters of the neutron source (in dimensionless units), have been achieved in the 2XIIB high-β plasma. The larger magnetic field of the present design permits scaling to the higher energy and density of the neutron-source design
  • Keywords
    fusion reactor materials; materials testing; neutron sources; plasma-beam interactions; 14 MeV; 150 keV; 2XIIB high-β plasma; D-T reactions; accelerated testing; beam-plasma neutron source; fully ionized tritium target plasma; fusion reactor materials; materials testing; plasma parameters; two-component plasma; Deuterium; Fusion reactor design; Fusion reactors; Life estimation; Materials testing; Neutrons; Plasma accelerators; Plasma density; Plasma materials processing; Plasma sources;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102307
  • Filename
    102307