Perspectives of a DCLL blanket for a future strong magnetic field fusion device
S. Smolentsev
Abstract
In the US, a Fusion Pilot Plant (FPP) is considered as a near-future machine to produce electricity on the net. While the FPP concept is being evolved, the common view is that a stronger compared to present fusion devices magnetic field B will be used for plasma confinement . All previous blanket studies have been limited to B <10 T. The paper presents new results of integrated studies for a Dual Coolant Lead Lithium (DCLL) blanket for B = 10–20 T. The blanket geometry, materials and thermal loads are adopted from the existing DCLL design for the US Fusion Nuclear Science Facility (FNSF). The computed results of magnetohydrodynamic flows, heat transfer, and corrosion for the reference DCLL blanket at PbLi T i n / T o u t =350 °C/550 °C suggest the maximum allowable magnetic field of 16 T. High temperature DCLL was found to exhibit acceptable MHD pressure drop even at B = 20 T but the corrosion losses may exceed the conventional limit of 20 µm/year. The analyses suggest that the DCLL blanket is a perspective blanket candidate for future fusion devices with a very high magnetic field >10 T.