(SE/P2-1) Burning Plasma Simulation and Environmental Assessment of Tokamak, Spherical Tokamak and Helical Reactors

K. Yamazaki1), S. Uemura1), T. Oishi1), J. Garcia2), H. Arimoto1), T. Shoji1)
 
1) Nagoya University, Nagoya, Japan
2) Universitat Politecnica de Catalunya, Barcelona, Spain

Abstract.  Burning plasma simulation in tokamak (TR), spherical tokamak (ST) and helical (HR) reactors were carried out focusing on Internal Transport Barrier (ITB) plasma operations using the TOTAL-T (Toroidal Transport Analysis Linkage - Tokamak) code coupled with GLF23 turbulent transport code and NCLASS neoclassical transport codes, and TOTAL-H (Helical) code with multi-helicity helical ripple transport analysis code. The effectiveness of these ITB transport coefficients is checked using experimental data of JT-60U and LHD. It clarified the requirement of deep penetration of high-field-side (HFS) pellet injection fueling to realize steady-state advanced burning operation in TR and ST. The neoclassical ripple transport plays an important role on the ITB operation in HR. Moreover, economical and environmental assessments were performed for these three type reactors by the PEC (Physics Engineering and Cost) system code in the case of four blanket designs (Li/V, Flibe/FS(Ferritic Steel), LiPb/SiC, FF(Fission-Fusion) Hybrid). In the present analysis, maximum field of superconducting coil is assumed 13 T, instead of maximum normal conductor strength of 8T in ST reactor. The tolerable neutron wall fluence is assumed 20 MWYr/m2 in the case of LiPb/SiC blanket system, which determines the replacement cycle of blanket modules. As for cost analysis, the fusion island (FI) cost of ST-1 is lowest. However, its fusion thermal power is largest and the TR is superior in cost of electricity (COE). Among four blanket designs Flibe/FS is superior in cost, because ferritic steel (FS) is much cheaper than vanadium (V). The life-cycle CO2 emission amount per output electric power and the energy payback ratio are also evaluated. The ST reactor is favorable in CO2 emission reduction, because rather compact and simple normal conducting coil system is adopted here. The ST and TR need more frequent blanket exchanges than HR with lower neutron wall load. However, HR is still expensive and has lower energy payback ratio and higher CO2 emission within the present evaluation model. These burning plasma and systematic environmental analysis for tokamak, spherical tokamak and helical reactors have been done comparatively for the first time by the help of the above transport and system codes.

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