Fast Ion Effects During Test Blanket Module Simulation Experiments in DIII-D

ORAL

Abstract

The fast beam-ion confinement in the presence of a scaled mock-up of two Test Blanket Modules (TBM) for ITER was studied in DIII-D. The TBM on \hbox{DIII-D} has four vertically arranged protective carbon tiles with thermocouples placed at the back of each tile. Temperature increases of up to 200$^{\rm o}$C were measured for the two tiles closest to the midplane when the TBM fields were present. These measurements agree qualitatively with results from the full orbit-following beam-ion code, SPIRAL, that predict beam-ion losses to be localized on the central two carbon tiles when the TBM fields present. Within the experimental uncertainties no significant change in the fast-ion population was found in the core of these plasmas which is consistent with SPIRAL analysis. These experiments indicate that the TBM fields do not affect the fast-ion confinement in a harmful way which is good news for ITER.

*Work supported in part by US DOE under DE-AC02-09CH11466, SC-G903402, DE-FC02-04ER54698, and DE-AC05-00OR22725.

Authors

  • G.J. Kramer

    • PPPL
  • R. Budny

    • PPPL
  • R. Nazikian

    • PPPL
  • W.W. Heidbrink

    • UC-Irvine
  • T. Kurki-Suonio

    • Helsinki U.
  • A. Salmi

    • Helsinki U.
  • M.J. Schaffer

    • General Atomics
  • M.A. Van Zeeland

    • General Atomics
    • GA
  • K. Shinohara

    • JAEA
  • J.A. Snipes

    • ITER Org.
  • D. Spong

    • ORNL