Analysis of Enhanced Heat Flux First Wall behavior under ITER Pulsed Loads

•Design of EHF FW 14 NE with non standard and complex geometrical structure conditioned by location in the zone of the equatorial port was developed.•Obtained pressure drop in FW 14 type NE coolant path is 329 kPa (FW to SB connection pipes are not taken into account).•Mass flow rate distribution between fingers pairs is acceptable and the absence of stagnant zones demonstrated.•In the middle part of the beam loaded by plasma radiation heat flux maximum temperature reaches 368 °C that does not exceed allowable one for 316 L(N)-IG equal to 450 °C.•Analysis of EHF FW 14 type NE behavior under Inductive I pulse loads demonstrates the possibility to remove CSI from EHF FW design that allows to simplify design of FW panel and it’s coolant system configuration.