• DocumentCode
    3198811
  • Title

    Nuclear heating in critical components of alternative ITER first wall attachment mechanism

  • Author

    Wilson, P.P.H. ; Sawan, M.E. ; Marriott, E.P. ; Ulrickson, M.A.

  • Author_Institution
    Fusion Technol. Inst., Univ. Wisconsin-Madison, Madison, WI, USA
  • fYear
    2009
  • fDate
    1-5 June 2009
  • Firstpage
    1
  • Lastpage
    3
  • Abstract
    A nuclear analysis was performed for an alternate ITER first wall attachment scheme to estimate the nuclear heating in critical components. With a variety of components near the first wall without direct cooling, there is concern that the operating temperatures will be above engineering limits. Using DAG-MCNP5, a 1-D analysis framework was used to estimate the nuclear heating in a detailed 3-D model of the first wall and shield attachment mechanism. The parts of the stainless steel hinge at the base of system experience nuclear heating between 1.85 and 5.07 W/cm3. The copper yoke and Inconel-718 yoke pin experience a heat rate of 2.44 W/cm3. If stainless steel bolts are used, the bolt heads will experience 2.9 W/cm3, with only a small reduction from plugging the bolt access holes. If molybdenum bolts are used, the bolt head heating is increased to 3.4 W/cm3. The heating in the hinge parts and stainless steel bolts is expected to lead to temperatures higher than engineering limits. Due to a higher thermal conductivity and melting temperature, the Mo bolts are expected to operate at acceptable temperatures.
  • Keywords
    Tokamak devices; chromium alloys; fusion reactor ignition; fusion reactor materials; iron alloys; melting; nickel alloys; plasma heating; stainless steel; thermal conductivity; 3D nuclear analysis; DAG-MCNP5; FeCrCJk; Inconel-718 yoke pin; alternative ITER first wall attachment mechanism; copper yoke; critical components; melting; nuclear heating; shield attachment mechanism; stainless steel bolts; thermal conductivity; Cooling; Copper; Fasteners; Heating; Laboratories; Performance analysis; Steel; Temperature; Thermal conductivity; Water; 3-D nuclear analysis; Monte Carlo;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    978-1-4244-2635-5
  • Electronic_ISBN
    978-1-4244-2636-2
  • Type

    conf

  • DOI
    10.1109/FUSION.2009.5226369
  • Filename
    5226369