Archivio Istituzionale della RicercaOne-dimension neutronic calculations of the DEMO blanket outboard module (Figure 1.28) have been performed. Figure 1.2.1 shows the schematization of the midplane section of the outboard blanket: it includes the first wall, the blanket and the shield in the outboard side, with the neutron source (the plasma) put in the first zone. A cylindrical model is used, centered on the plasma axis. The code ANISN has been used, with the 46-groups neutron cross section library UKCTR-1 as data base; P3-S8 approximation has been assumed. The DEMO plasma neutron source, resulting in a neutron wall loading of 2 MW /m2, has been considered.
Tritium production rate evaluation / Zucchetti, Massimo - In: Fusion Technology and Safety at the Joint Research Centre, 1988 / Giampaolo Casini, Paolo Rocco. - STAMPA. - Luxemburg, Lussemburgo : Office for the Official Publications of the European Communities, Luxembourg, EUR-12411 EN, 1989. - pp. 30-37 [10.13140/RG.2.2.21504.02561]
Tritium production rate evaluation
ZUCCHETTI, MASSIMO
1989
Abstract
One-dimension neutronic calculations of the DEMO blanket outboard module (Figure 1.28) have been performed. Figure 1.2.1 shows the schematization of the midplane section of the outboard blanket: it includes the first wall, the blanket and the shield in the outboard side, with the neutron source (the plasma) put in the first zone. A cylindrical model is used, centered on the plasma axis. The code ANISN has been used, with the 46-groups neutron cross section library UKCTR-1 as data base; P3-S8 approximation has been assumed. The DEMO plasma neutron source, resulting in a neutron wall loading of 2 MW /m2, has been considered.
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https://hdl.handle.net/11583/2653500
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