Designing ARIES-CS Compact Radial Build and Nuclear System: Neutronics, Shielding, and Activation

Systems Studies and Optimization of the ARIES-CS Power Plant

“…1.1. Figure 5 illustrates the two-region blanket and shield geometry 11 developed for the reference ARIES-CS case. The distance needed for a 5-cm scrape-off layer, blanket, shield, manifolds, assembly gaps, vacuum vessel wall, .75 m for the 1-GW~electric!…”

“…Hollow n e~r !, and hence hollow n Z~r !, profiles are of interest because they produce broader radiation profiles, which reduce the ratio of the maximum-to-average radiative power density on the wall. 11 Since the average radiative wall power density is fixed for a given f rad and R axis &, reducing this ratio reduces the peak cooling needs on the wall. Figure 18 illustrates the power flows within the plasma and to the first wall and divertor.…”

Safety Assessment of the ARIES Compact Stellarator Design

“…More details on the neutronics analysis in support of the power plant design can be found in Ref. 7. The proposed divertor configuration consists of a "T-tube" illustrated in Fig.…”

“…The ALARA activation code, 10 DANTSYS transport code, 11 and their FENDL-2 data library have been used throughout the study. 7 The operational history has been represented as 0.85 yr irradiation time followed by 0.15 yr downtime, and repeats for 4 or 47 yr, depending on the component lifetime.…”

Preliminary evaluation of decay heat in a HCPB DEMO fusion reactor

“…In previous studies [1][2][3][4], only prompt heat production was accounted for in power production for a D-T fusion power plant. Decay heat was neglected, even though it could be an important contribution to heating of components, especially in in-vessel of a tokamak device, such as the first wall, blanket and divertor.…”