Conceptual Designs of Tokamak Fusion Reactors

Abstract

Tokamak fusion reactor design studies conducted in JAERI with support from national laboratories, universities and industries in the fifteen years since 1973 to the present are described. These studies gave considerable impact on the national and international fusion programs.

From the proposal of He-cooled Li²0 blanket for fusion power reactor in 1973 to the most recent proposal of easily replaceable guard limiter concept to the ITER project, a number of unique proposals that have influenced the world wide fusion reactor design studies are introduced. They are described in the context of major fusion reactor design efforts and design methodology developments of the past fifteen years.

KEYWORDS:

• tokamak fusion reactor
• lithium oxides
• blankets
• FER tokamak
• INTOR
• ITER
• divertor
• negative-ion-based NBI
• SPTR
• guard limiter
• Japan