Published September 2011 | Version v1
Journal article

Progress and issues in PWI studies of tungsten for ITER

  • 1. National Inst. for Fusion Science, Toki, Gifu (Japan)
  • 2. Osaka Univ., Suita, Osaka (Japan)

Description

Advantages of tungsten as plasma-facing materials for ITER tokamak are based on its properties such as high melting point, low sputtering yield and low hydrogen adsorption. However, these properties will change during the plasma-wall interaction (PWI). In the present chapter, we deal with four important issues on PWI: damaging of metals by the helium plasma, surface modification by the formation of a mixed-material deposition layer, neutron damage and tritium storage and melting and crack formation by the heat pulse. Effects of these issues on the life and performance of tungsten-based plasma-facing components, the impurity release into the core plasma, the fuel particle balance and the tritium inventory are discussed. (J.P.N.)

Additional details

Publishing Information

Journal Title
Purazuma, Kaku Yugo Gakkai-Shi
Journal Volume
87
Journal Issue
9
Journal Page Range
p. 591-599
ISSN
0918-7928

Optional Information

Notes
66 refs., 12 figs., 1 tab.