Archivio Istituzionale della RicercaThe IGNITOR-ULT machine has been modelled by a 3-D neutron transport code (MCNP) and the neutron flux has been calculated in selected points of interest. Starting from these data the neutron induced radioactivity in the structures has been calculated by the inventory code ANITA in order to assess the maintenance, remote handling policy and waste management.
3-D NEUTRON TRANSPORT CALCULATIONS FOR ACTIVATION AND DOSE ASSESSMENT FOR IGNITOR / Batistoni, P.; Ciattaglia, S.; Rollet, S.; Zucchetti, Massimo. - STAMPA. - 2:(1993), pp. 1281-1285. (Intervento presentato al convegno 17th Symposium On Fusion Technology tenutosi a Roma (Italia) nel 13-18 settembre 1992) [10.1016/B978-0-444-89995-8.50250-2].
3-D NEUTRON TRANSPORT CALCULATIONS FOR ACTIVATION AND DOSE ASSESSMENT FOR IGNITOR
ZUCCHETTI, MASSIMO
1993
Abstract
The IGNITOR-ULT machine has been modelled by a 3-D neutron transport code (MCNP) and the neutron flux has been calculated in selected points of interest. Starting from these data the neutron induced radioactivity in the structures has been calculated by the inventory code ANITA in order to assess the maintenance, remote handling policy and waste management.
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