Benefits of Radial Build Minimization and Requirements Imposed on Aries Compact Stellarator Design

UWFDM-1233 Benefits of Radial Build Minimization and Requirements Imposed on ARIES Compact Stellarator Design

Exploration of Compact Stellarators as Power Plants: Initial Results from ARIES-CS Study

A detailed and integrated study of compact stellarators as power plants, ARIES-CS, was initiated recently to advance our understanding of attractive compact stellarator configurations and to define key R&D areas. We have completed phase 1 of ARIES-CS study— our results are described in this paper. We have identified several promising stellarator configurations. High particle loss of these confi...

UWFDM-1324 Nuclear Challenges and Progress in Designing Stellarator Power Plants

Over the past 2-3 decades, stellarator power plants have been studied in the U.S., Europe, and Japan as an alternate to the mainline magnetic fusion tokamaks, offering steady state operation and eliminating the risk of plasma disruptions. The earlier 1980s studies suggested large stellarators with an average major radius exceeding 20 m. The most recent development of the compact stellarator con...

Safety Assessment of the Aries Compact Stellarator Design

ARIES-CS is a 1000 MW(electric) compact stellarator conceptual fusion power plant design. This power plant design contains many innovative features to improve the physics, engineering, and safety performance of the stellarator concept. ARIES-CS utilizes a dualcooled lead lithium blanket that employs low-activation ferritic steel as a structural material, with the first wall cooled by helium and...

UWFDM-1336 Overview of ARIES-CS In-Vessel Components: Integration of Nuclear, Economics, and Safety Constraints in Compact Stellarator

The recent development of the compact stellarator concept delivered ARIES-CS – a compact stellarator with 7.75 m average major radius, approaching that of tokamaks. In stellarators, the most influential engineering parameter that determines the machine size and cost is the minimum distance between the plasma boundary and mid-coil (∆min). Accommodating the breeding blanket and necessary shield w...