The presently predicted total heating power of the demonstration fusion reactor DEMO is ∼3 times the ITER value, while the major radius is only 1.5 times larger (R. Wenninger, et al., The DEMO Wall Load Challenge, Nucl. Fusion 57 (2017) 046002 (11pp)) [1]. The current DEMO technological wall heat load removal capability is limited to ∼1 MW/m2, due to structural material limitations and the tritium breeding requirements, while the ITER first wall (FW) is designed for values up to 4.7 MW/m2. This paper focuses on the evaluation of the effect of the engineering constraints on the required limitation of charged particle heat load. First, a 2D field-mapping tool is used together with a simple model to take into account the peaking factors present on an engineering 3D wall design. A sensitivity analysis is performed on a set of realistic FW 3D features considering a preliminary estimate of misalignments. The impact on the heat flux to the wall due to different machine geometries, plasma shapes variation, stationary plasma and plasma transients, is presented. An automatic procedure to define the 2D poloidal contour of the FW for minimized particle loads is presented. A subset of the resulting engineering wall design is analyzed using the 3D field line tracing code PFCflux.
Effect of engineering constraints on charged particle wall heat loads in DEMO / Maviglia, F.; Federici, G.; Wenninger, R.; Albanese, R.; Ambrosino, R.; Bachmann, C.; Barbato, L.; Cismondi, F.; Firdaouss, M.; Loschiavo, V. P.; Lowry, C.. - In: FUSION ENGINEERING AND DESIGN. - ISSN 0920-3796. - 124:(2017), pp. 385-390. [10.1016/j.fusengdes.2017.02.077]
Effect of engineering constraints on charged particle wall heat loads in DEMO
Maviglia, F.;Albanese, R.;Ambrosino, R.;Loschiavo, V. P.;
2017
Abstract
The presently predicted total heating power of the demonstration fusion reactor DEMO is ∼3 times the ITER value, while the major radius is only 1.5 times larger (R. Wenninger, et al., The DEMO Wall Load Challenge, Nucl. Fusion 57 (2017) 046002 (11pp)) [1]. The current DEMO technological wall heat load removal capability is limited to ∼1 MW/m2, due to structural material limitations and the tritium breeding requirements, while the ITER first wall (FW) is designed for values up to 4.7 MW/m2. This paper focuses on the evaluation of the effect of the engineering constraints on the required limitation of charged particle heat load. First, a 2D field-mapping tool is used together with a simple model to take into account the peaking factors present on an engineering 3D wall design. A sensitivity analysis is performed on a set of realistic FW 3D features considering a preliminary estimate of misalignments. The impact on the heat flux to the wall due to different machine geometries, plasma shapes variation, stationary plasma and plasma transients, is presented. An automatic procedure to define the 2D poloidal contour of the FW for minimized particle loads is presented. A subset of the resulting engineering wall design is analyzed using the 3D field line tracing code PFCflux.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.