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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.

Additional information

Authors: CIATTAGLIA S, ENEA, Centro Ricerche Energia Frascati, Roma (IT);CEPRAGA D G, ENEA, Centro Ricerche Energia Bologna (IT);CAMBI G, University of Bologna, Department of Physics (IT);CAVALLONE G, NIER Srl, Bologna (IT);COSTA M, NIER Srl, Bologna (IT)
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
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