University of Wisconsin-Madison

Fusion Technology Institute

FTI Research

• APEX
• ARIES
• Code Development
• D-3He Fuel Cycle
• Environmental Impact
• FIRE
• FRC
• HAPL
• IEC
• ITER
• Liquid Metal Safety
• Lunar Mining
• Medical Isotopes
• RadHydro
• Shock Tube
• Space Propulsion
• X1 Chamber

Advanced D-3He Fuel Cycle

The interest in fusion safety has stimulated worldwide research for other fuel cycles such as D-D, D-3He, p-11B, and 3He-3He. These fuel cycles, except 3He-3He, are not completely aneutronic due to their side reactions. Neutron wall loadings, however, can be kept low (by orders of magnitude) compared to D-T fuelled plants with the same output power, eliminating the need for a breeding blanket and the replacement of the first wall and shielding components during the entire plant lifetime. The availability of 3He and the attainment of the higher plasma parameters required for burning are challenging problems for the D-3He fuel cycle. High beta and/or high field innovative confinement concepts, such as the field-reversed configuration and, to a lesser extent, the tokamaks are suitable devices for advanced fuel cycles. In the early 1990s, the ARIES-III D-3He tokamak was developed within the framework of the ARIES study. The UW D-3He Apollo series, along with ARIES-III, demonstrated attractive safety characteristics, including low activity and decay heat levels, low-level waste, and low releasable radioactive inventory from credible accidents. Another advantage for the D-3He system is the possibility of obtaining electrical power by direct energy conversion of the protons and radiation produced by fusion reactions. These advantages suggest that studies for the development of advanced fuel cycles should be carried out in parallel with the present mainstream D-T fusion power development, as the low neutron production helps overcome some of the engineering, materials, and safety hurdles to fusion development.