• DocumentCode
    3460842
  • Title

    Conceptual Design of a Plasma Exhaust and Fuel Recovery System for an Inertial Fusion Energy (IFE) Power Reactor

  • Author

    Gentile, C.A. ; Langish, S.W. ; Kozub, T. ; Priniski, C. ; Dodson, T. ; Gettelfinger, G. ; Paul, B. ; Ciebiera, L. ; Wermer, J. ; Nobile, A. ; Sessions, K. ; Sethian, J. ; Robson, A.E.

  • Author_Institution
    Princeton Plasma Phys. Lab., Princeton
  • fYear
    2007
  • fDate
    17-21 June 2007
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    A conceptual design has been developed for the recovery of un-expended fuel, ash, and associated post-detonation products from a ~ 2 GW IFE power reactor. The conceptual design incorporates systems for the safe, efficient collection, processing, and purification of IFE plasma exhaust fuel components. The system has been designed and sized such that tritium bred within blankets can also be collected, processed, and introduced into the fuel cycle. The system is nominally sized to process ~2 kg of tritium per day and is designed to link directly to the target chamber mechanical pumping system. The plasma exhaust can be directly processed from the exhaust of the vacuum pumping system or can be processed in batch mode from buffer vessels in the receiving and analysis system (RAS). Systems for the accurate measurement of material in-process (MIP) have been included. Design emphasis is on safety, reliability, redundancy, and efficiency in order to maximize availability. The primary goal of the fuel recovery system (FRS) design is to economically recycle components of IFE fuel back to the target manufacturers in a fashion by which fuel components are rapidly made available for re-use thus lowering the total active inventory. The FRS design is presented as a facility sub-system in the context of supporting the safe and efficient operation of the IFE target chamber.
  • Keywords
    detonation; fusion reactor blankets; fusion reactor design; fusion reactor fuel; fusion reactor operation; fusion reactor safety; fusion reactor targets; plasma materials processing; tritium; FRS design; IFE target chamber; MIP process; RAS; ash; blankets; buffer vessels; fuel recovery system; inertial fusion energy power reactor; mechanical pumping system; plasma exhaust fuel components; postdetonation products; receiving analysis system; reliability; safety operation; tritium; vacuum pumping system; Ash; Fuels; Fusion reactor design; Inductors; Plasma materials processing; Plasma measurements; Purification; Redundancy; Safety; Vacuum systems;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
  • Conference_Location
    Albuquerque, NM
  • Print_ISBN
    978-1-4244-1193-1
  • Electronic_ISBN
    978-1-4244-1194-8
  • Type

    conf

  • DOI
    10.1109/FUSION.2007.4337904
  • Filename
    4337904