• DocumentCode
    3503075
  • Title

    New missions for Z pinches

  • Author

    De Groot, J.S. ; Mehlhorn, T.

  • Author_Institution
    Plasma Res. Group, Sandia Nat. Labs., Livermore, CA, USA
  • fYear
    2004
  • fDate
    1-1 July 2004
  • Firstpage
    203
  • Abstract
    Summary form only given. We are considering non-electric missions for high power Z pinches with DT fuel. The missions are: transmutation of spent nuclear reactor fuel, production of medical isotopes, hydrogen production, and materials testing. Near term (5-20 yr) missions that are well suited to Z-pinch driven DT fusion neutrons are: the production of Mo/sup 99/, the most widely used medical isotope, intense neutron flux materials tester, and to validate the use of GW level Z pinches to transmutate spent nuclear reactor fuel. These missions would use a gain /spl sim/0.2-1 DT Z pinch that emits a few MJ of neutrons in a burst mode. Mo/sup 99/ will be produced by bombarding Mo/sup 100/ with 14 MeV neutrons since the (n,2n) cross section is large (/spl sim/barn) at 14 MeV. The long term (20-30 yr.) missions that are well suited to rep-rated Z pinches at the GW level are transmutation of spent nuclear fuel, economic production of hydrogen, and a high neutron flux for materials testing. The transmutation of the transuranics is much more efficient in a fusion system because the ratio of the fission cross section to the absorption cross section is much larger for 14 MeV neutrons than the /spl sim/1 MeV neutrons in a fast reactor.
  • Keywords
    Z pinch; hydrogen economy; materials testing; molybdenum; neutron flux; plasma production; radioactive waste processing; radioisotopes; 1 MeV; 14 MeV; 20 to 30 yr; 5 to 20 yr; GW level Z pinches; Mo; absorption cross section; burst mode; fission cross section; fusion neutrons; fusion system; high power Z pinches; hydrogen economic production; hydrogen production; materials testing; medical isotope; medical isotopes; neutron flux; neutron flux materials test; nonelectric missions; spent nuclear fuel; spent nuclear reactor fuel; transmutation; Fission reactors; Fuel economy; Hydrogen; Isotopes; Materials testing; Medical tests; Neutrons; Nuclear fuels; Power generation economics; Production;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Plasma Science, 2004. ICOPS 2004. IEEE Conference Record - Abstracts. The 31st IEEE International Conference on
  • Conference_Location
    Baltimore, MD, USA
  • ISSN
    0730-9244
  • Print_ISBN
    0-7803-8334-6
  • Type

    conf

  • DOI
    10.1109/PLASMA.2004.1339789
  • Filename
    1339789