  The heat flux mitigation during the Thermal Quench (TQ) by the Shattered
Pellet Injection (SPI) is one of the major elements of disruption mitigation
strategy for ITER. It's efficiency greatly depends on the SPI and the target
plasma, and is ultimately checked by the heat deposition on to the PFCs. To
investigate this, JOREK simulations of neon-mixed dual-SPIs into ITER baseline
H-mode and a "degraded H-mode" with and without good injector synchronization
are performed with focus on the first wall heat flux and its energy impact. It
is found that low neon fraction SPIs into the baseline H-mode plasmas exhibit
strong major radial plasmoid drift as the fragments arrive at the pedestal,
accompanied by edge stochasticity. Significant density expulsion and outgoing
heat flux occurs as a result, reducing the mitigation efficiency. Such drift
motion could be mitigated by injecting higher neon fraction pellets', or by
considering the pre-disruption confinement degradation, thus improving the
radiation fraction. The radiation heat flux is found to peak in the vicinity of
the fragment injection location in the early injection phase, while it relaxes
later on due to parallel impurity transport. The overall radiation asymmetry
could be significantly mitigated by good synchronization. Time integration of
the local heat flux is carried out to provide its energy impact for wall heat
damage assessment. For the baseline H-mode case with full pellet injection,
melting of the stainless steel of the diagnostic port could occur near the
injection port, which is acceptable, without any melting of the first wall
tungsten tiles. For the degraded H-mode cases with quarter-pellet SPIs, which
have 1/4 total volume of a full pellet, the maximum energy impact approaches
the tolerable limit of the stainless steel with un-synchronized SPIs, and stays
well below such limit for the perfectly synchronized ones.
