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Maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets

J. Miyazawa, T. Goto, H. Tamura, Teruya Tanaka, N. Yanagi, T. Murase, R. Sakamoto, S. Masuzaki, Takeru Ohgo, A. Sagara

Fusion Engineering and Design · 2018 · 13 citations · 14 references

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References

14

Energy confinement scaling from the international stellarator database

U. Stroth, M. Murakami, R. A. Dory et al. · Nuclear Fusion · 1996 · 275 citations

, , +17

Characterization of energy confinement in net-current free plasmas using the extended International Stellarator Database

H. Yamada, J. H. Harris, A. Dinklage et al. · Nuclear Fusion · 2005 · 256 citations

, , +15

Goal and Achievements of Large Helical Device Project

A. Komori, H. Yamada, S. Imagawa et al. · Fusion Science & Technology · 2010 · 130 citations

, , +17

Helical reactor design FFHR-d1 and c1 for steady-state DEMO

A. Sagara, H. Tamura, Teruya Tanaka et al. · Fusion Engineering and Design · 2014 · 125 citations

, , +10

A comparative study of transport in stellarators and tokamaks

U. Stroth · Plasma Physics and Controlled Fusion · 1998 · 125 citations

, , +15