Concept of core and divertor plasma for fusion DEMO plant at JAERI

M. Sato, S. Sakurai, S. Nishio, K. Tobita, T. Inoue, Y. Nakamura, K. Shinya, H. Fujieda

Research output: Contribution to journalConference articlepeer-review

13 Citations (Scopus)


Fusion DEMO plant design at JAERI directs toward compactness and economy of the reactor with a fusion output at 3 GW level. The smaller size of the center solenoid (CS) has a large impact on reducing the reactor size and weight. Three candidates for CS, namely "-less", "slim" and "full" CS, are considered according to the role of CS coil that is plasma ramp up and plasma shaping. From points of views of technical feasibility, obtained triangularity (δx) and weight of the reactor, the slim-CS is selected as the candidate for DEMO at JAERI. For slim-CS, high δx (≥0.43), which is enough to suppress giant ELMs, is obtained, and highly radiative outer divertor is required in steady state power handling. The consistent equilibrium was found to satisfy the divertor requirements and radial build. During the plasma current ramp up phase, the acceleration voltage of neutral beam injection (NBI) has to be changed more than two times. In order to inject sufficient power during the low-energy beam injection, the present technology must be replaced by a new constant-current, variable-voltage technology.

Original languageEnglish
Pages (from-to)1277-1284
Number of pages8
JournalFusion Engineering and Design
Issue number8-14 PART B
Publication statusPublished - 2006 Feb
EventProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
Duration: 2005 May 222005 May 27


  • Center solenoid coil
  • Divertor
  • Equilibrium
  • Fusion DEMO plant
  • NBI
  • Operation scenario


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