PPCA.I-2
Overview of ARIES-CS In-vessel Components: Integration of Nuclear,
Economic, and Safety Constraints in Compact Stellarator Design |
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Laila El-Guebaly and the ARIES-CS Team1
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1Fusion Technology Institute, University of Wisconsin, Madison, WI, elguebaly@engr.wisc.edu |
Abstract:
As an alternate to the mainline magnetic fusion tokamaks, the stellarator concept offers a
steady state operation without external driven current, eliminating the risk of plasma disruptions.
The earlier 1980s studies delivered large stellarators with an average major radius exceeding 20
m. The most recent development of the compact stellarator concept has led to the 3 years power
plant study of ARIES-CS, a compact stellarator with 7.75 m average major radius, approaching
that of tokamaks.
Two blanket concepts were studied for ARIES-CS: a dual-cooled LiPb/He/FS system as a
reference concept and a self-cooled LiPb blanket with SiC/SiC structure as a backup. The first
wall configuration deviates from the standard practice of uniform toroidal/poloidal shape to
achieve compactness. Modeling such a complex geometry for 3-D nuclear analysis was a
challenging engineering task. A novel approach based on coupling the CAD model with the
MCNP Monte Carlo code was developed to model, for the first time ever, the complex stellarator
geometry for nuclear assessments.
The most important engineering parameter that influences the machine size and cost is
the minimum distance between the plasma boundary and mid-coil. Accommodating the blanket
and shielding components represented another challenging task. An innovative approach
utilizing a non-uniform blanket combined with a highly efficient WC shield for this highly
constrained area reduced the radial standoff, major radius, and cost of electricity by 25-30%,
which is significant. Equally important is the consequence of the substantial reduction in ARIESCS
radwaste volume compared to previous stellarator designs.
The objective of this paper is to review the nuclear elements that received considerable
attention during the design process and provide a perspective on their successful integration into
the final design. Among these elements are the radial build definition, the well-optimized invessel
components, the carefully selected nuclear and engineering parameters to produce an
economic optimum, and the overarching safety and environmental constraints to deliver an
attractive, reliable, and truly compact stellarator power plant.
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