Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design

Progress of the CFETR design

(2019) Ge Zhuang et al.   NUCLEAR FUSION

Figure of merit for the divertor protection in the preliminary design of EU-DEMO reactor

(2019) Mattia Siccinio et al.   NUCLEAR FUSION

Correlation of the tokamak H-mode density limit with ballooning stability at the separatrix

(2018) T. Eich et al.   NUCLEAR FUSION

Plasma exhaust and divertor studies in Japan and Europe broader approach, DEMO design activity

(2018) Nobuyuki Asakura et al.   FUSION ENGINEERING AND DESIGN

Design Strategy and Recent Design Activity on Japan’s DEMO

(2017) Kenji Tobita et al.   FUSION SCIENCE AND TECHNOLOGY

Studies of power exhaust and divertor design for a 1.5 GW-level fusion power DEMO

(2017) N. Asakura et al.   NUCLEAR FUSION

Compatibility of separatrix density scaling for divertor detachment with H-mode pedestal operation in DIII-D

(2017) A.W. Leonard et al.   NUCLEAR FUSION

The influence of the radial particle transport on the divertor plasma detachment

(2015) K. Hoshino et al.   JOURNAL OF NUCLEAR MATERIALS

Consequences of a reduction of the upstream power SOL width in ITER

(2013) A.S. Kukushkin et al.   JOURNAL OF NUCLEAR MATERIALS

Impact of carbon and tungsten as divertor materials on the scrape-off layer conditions in JET

(2013) M. Groth et al.   NUCLEAR FUSION

Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER

(2013) T. Eich et al.   NUCLEAR FUSION

Efforts towards improvement of systems codes for the Broader Approach DEMO design

(2012) Makoto Nakamura et al.   FUSION ENGINEERING AND DESIGN