Fusion reactor design and technology program in Japan

Abstract

Fusion power reactor studies conducted in Japan are reviewed and their potential merits and research and development issues are listed. Beginning with a tokamak power reactor study carried out in 1973, there have been a considerable number of studies on both magnetic and inertial confinement fusion schemes. It is of interest to note that there is at least one power reactor concept for each major confinement scheme studied in Japan. Most of these use the D–T fuel cycle, but in recent years D– 3 He fuel reactors have also been studied. We review the key technology development program required to realize a power reactor, those for structural materials, superconducting magnet coils, neutral beam injectors, plasma facing components, tritium breeding blanket, vacuum technology, tritium safety and processing technology, and remote handling technology. The present levels of the technologies are compared with those required for power reactors.