UWFDM-1082 Activation and Safety Assessment of the ARIES-ST Design

UWFDM-1080 Need for Inboard Shield to Protect the Center Post of ST Power Plants

The center post (CP) is the most critical in-vessel component in spherical tokamaks (ST). Advanced ST power plant designs normally call for high neutron wall loads (>5 MW/m) forcing the CP to operate in a high radiation environment. Radiation degrades the physical properties of the current carrying conductor and severely affects the overall performance of the CP. An unshielded CP does not appea...

UWFDM-1147 Activation, Decay Heat, and Waste Disposal Analyses for the ARIES-AT Power Plant

Detailed activation, decay heat and waste disposal calculations of the ARIES-AT design are performed to evaluate the safety aspects of the device. The high initial activity of the SiC highly irradiated components translates directly into a higher initial decay heat for these structures than for the well-protected steel-based components. However, after a one-hour cool-down period, the SiC decay ...

UWFDM-1236 Initial Activation Assessment for ARIES Compact Stellarator Power Plant

DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government, nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclos...

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

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...