Outboard first wall (AISI 316L) activation evaluations with different activation codes, neutron data libraries, and data processing
This paper presents the main results of a benchmark exercise set up to compare nuclear cross-section data libraries and data processing techiques (123-group AMPX, VITAMIN-C, and VITAMIN-J) and activation codes (ANITA, ORIGEN and FISPACT-2) for activation evaluations in the fusion field. The torus outboard region of a fusion machine such as NET-II/ITER has been considered, and attention 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-ENC-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 performed 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.
Bibliographic Reference: Report: ENEA RT/ERG/FUS/93/13 EN (1993) 41 pp.
Availability: Available from Servizio Studi e Documentazione, ENEA, Centro Ricerche Energia Frascati, C.P. 65-00044 Frascati, Roma (IT)
Record Number: 199411240 / Last updated on: 1994-11-25
Original language: en
Available languages: en