Early Comparison of the Transport of Helium Ions into Different RAFM Steels and Sillicon Carbide for TBM

In this paper the early comparison of the transport of Helium Ions into different reduced activation ferritic-martensitic steels, and silicon carbide is presented, both with He Ions of 0,66 KeV, 150KeV and 1 MeV to improve the understanding of radiation damage in different alloys of Test Blanket Modules. The radiation damage in nuclear alloys is well known, however the damage in new materials to be used in ITER and DEMO has to be researched. This is the case of RAFM Steels as ODS and also SiC can be a key component of several Test Blanket Modules. Differences in the transport of helium ions over ODS can be relevant for the use of a European test blanket module as the Helium Cooled Lithium Lead-HCLL with the best early assessment of damage with the TRIM program. Similarly the differences in the transport of helium ions over SiC can be relevant for the use of a test blanket module as the Dual Coolant Lithium LeadDCLL. (Author)