Erosion of plasma-facing components in ITER

Concept of core and divertor plasma for fusion DEMO plant at JAERI

“…Transient heat loads such as ELM heat loads should be also less than 0.8 MJ/m 2 to avoid melting [11]. The power flow into the divertor region is 400 MW for 3 GW fusion power, assuming 200 MW of main plasma radiation.…”

Dynamic chamber armor behavior in IFE and MFE

“…Results of analysis done to compute erosion of the first-wall (due to fuel chargeexchange neutrals and ions and impurity ions) and the subsequent transport of material on the divertor surfaces are presented in Ref. [3].…”

“…In MFE, the ITER design representing an example of the next-step reactor considers beryllium, tungsten and carbon as armor material for its plasma-facing components; however, beryllium would provide limited possibilities for further application to power plant reactor because of its low melting point and operating temperature limit, and high sputtering yield [3]. Tungsten and carbon which provide high temperature accommodation are also considered as armor for IFE.…”

Ex-situ tritium removal from JET tiles using RF inductive heating

“…55 m 2 . Based on results from JET it is estimated that at least 2 g tritium per pulse will be incorporated into the carbon material of ITER [2,3].…”