ARIES-ST nuclear analysis and shield design
نویسنده
چکیده
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 breeding ratio (TBR), and nuclear heat loads to in-vessel components. The main theme of the shielding analysis is to develop guidance and recommendations on radiation protection for the TF magnet, in particular, the center-post. The need for an inboard shield, the selection of an optimal shield, the rationale for the shielding material choices, and the consequences of the shielding material choices on the overall design are reported herein. During the course of the ARIES-ST study, the design has been analyzed rigorously with a set of 3-D nuclear analyses to guide the developing design. The results of the assessment had a major impact on the design choices. For instance, the insufficient breeding along with other design constraints have ruled out the use of several attractive solid breeder blankets, the excessive neutron damage to the center-post provided strong incentives to shield the center-post, and the high radiation damage to the plasma facing components has limited the service lifetime of the ferritic steel (FS) structure to a few full power years. Furthermore, the high heat load to the inboard shield (400 MW, 10% of thermal power) forced the design to recover the inboard heating as high-grade heat to enhance the power balance. Also, the sensitivity of the outboard-only LiPb breeding blanket to the inboard shielding materials has limited the shielding options and excluded several high performance inboard-shielding materials. The performed analyses and results are reported and discussed in relation to the integrated design and the established top-level requirements for the ARIES power plants. # 2002 Elsevier Science B.V. All rights reserved.
منابع مشابه
Neutronics Characteristics, Shielding System, Activation and Environmental Aspects of ARIES-ACT-2 Power Plant
The ARIES team has completed the detailed design of ARIES-ACT-2 with conservative physics and technology. The integration of nuclear assessments (neutronics, shielding, and activation) is an essential element to the success of a well-optimized design. High fidelity in nuclear parameters mandates performing state-of-the-art nuclear analyses. This has been achieved through coupling the CAD system...
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-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...
متن کاملARIES-ST safety design and analysis
Activation and safety analyses were performed for the ARIES-ST design. The ARIES-ST power plant includes a water-cooled copper centerpost. The first wall and shield are made of low activation ferritic steel and cooled with helium. The blanket is also made of ferritic steel with SiC inserts and Li17Pb83 breeder. The divertor plate is made of low activation ferritic steel and uses a tungsten brus...
متن کاملFUSION 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 کامل