Speaker
Qin Zeng
(School of Nuclear Science and Technology)
Description
Chinese Fusion Engineering Testing Reactor (CFETR) is a test tokamak reactor to bridge the gap between ITER and future fusion power plant and to demonstrate generation of fusion power in China. In order to select the most suitable blanket proposal for CFETR, the three blanket concepts (i.e. the helium cooled solid breeder blanket, the liquid LiPb blanket, and the water cooled ceramic breeder blanket) are under development and evaluation simultaneously. A Helium Cooled Solid Breeder (HCSB) blanket was proposed by School of Nuclear Science and Technology, University of Science and Technology of China, and its conceptual design has been carried out. In this paper, the specific issues and analysis on damage to TF coils of CFETR with HCSB blanket were carried out based on the three-dimensional model of the CFETR with the widely used code MCNP and the IAEA latest released FENDL/2.1 data library. Damage to some specific regions of the TF coils near large openings and at the inboard mid-plane are calculated and analyzed. Parameters such as the distributions of nuclear heat density, fast neutron flux, dose rate to the epoxy insulator, and peak displacement dose to Cu conductor for the TF coil near these regions were calculated and analyzed. The shield thicknesses at these regions are optimized.
Keywords: Irradiation damage, neutronics, TF coil, CFETR, Helium cooled solid breeder
Co-authors
Haoran Zhang
(School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, China)
Hongli Chen
(School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, China)
Lei Pan
(School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, China)
Qin Zeng
(School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, China)
Wei Li
(School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, China)
Zhongliang Lv
(School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, China)
