Outboard first wall (AISI 316L) activation evaluations with different activation codes, neutron data libraries, and data processing

摘要

This paper presents the main results of a benchmark exercise that has been set up in order to compare nuclear cross section data libraries and data processing techniques (123-group AMPX, VITAMI-C, and VITAMIN-J) and activation codes. (ANITA, ORIGEN and FISPACT-2) for activation evaluations in fusion field. The Torus outboard region of a fusion machine like NET-II/TTER has been considered, and the attention was focused on the first wall stainless steel AISI 316L. The update of the ORIGEN neutron Data library was obtained by collapsing the 100-group GREAC-ECN-5 Activation library with the flux-weighted spectrum provided by XSDRNPM-S code; this method allows the radioactivity inventory and the decay heat power evaluations to be done by the ORIGEN-S code. The test case has been used to verify the effect of the neutron power load and of the fluence on the isotope specific activity of the irradiated steel, too.