UWFDM-1080 Need for Inboard Shield to Protect the Center Post of ST Power Plants
نویسندگان
چکیده
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 appear to offer an attractive design. This paper presents the rationale for shielding the CP of ARIES-ST, the reasons for the design choices, and the consequences of the choices on the power plant design.
منابع مشابه
FUSION TECHNOLOGY INSTITUTE UNIVERSITY OF WISCONSIN MADISON WISCONSIN 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...
متن کاملARIES-ST nuclear analysis and shield design
A power plant design based on the spherical torus (ST) concept has been developed by the ARIES team. This paper documents the results of the nuclear and radiation protection analyses carried out for the ARIES-ST design. The nuclear analysis addresses the key neutronics issues, such as the neutron wall loading profile, radiation damage to structural components and their lifetimes, tritium breedi...
متن کاملUWFDM-1082 Activation and Safety Assessment of the ARIES-ST Design
Activation and safety analyses were performed for the ARIES-ST design. The ARIES-ST power plant includes a water cooled copper center post and uses a SiC/LiPb blanket. The first wall and shield are made of low activation ferritic steel and cooled with helium. The center post, first wall, inboard shield and blanket were assumed to survive for 2.6 full power years (FPY). On the other hand, the ou...
متن کاملUWFDM-827 Overview of the US-ITER Magnet Shield: Concept and Problems
The International Thermonuclear Experimental Reactor (ITER) is designed to operate in two phases; physics and technology. The prime function of the shield is to protect the TF magnets. The predominant radiation limits are the nuclear heat load to the magnet and the end-of-life dose to the electrical insulator. These limits are specified by the magnet designers as 65 kW and 5×109 rads. Detailed ...
متن کاملARIES-ST plasma-facing component design and analysis
ARIES-ST is a 1000 MW fusion power plant conceptual design based on a low aspect ratio ‘spherical torus’ (ST) plasma. The plasma-facing components include the inboard and outboard first wall, divertor plates, and plasma stability plates. Several unique aspects of ST plasma influence the engineering design. The limited inboard space precludes a full inboard divertor slot, such that substantial p...
متن کامل