Neutronics analysis of the conceptual design of a component test facility based on the spherical tokamak

作者：Zheng S^*; Voss G M; Pampin R

来源：Fusion Engineering and Design, 2010, 85(10-12): 2300-2304.

DOI：10.1016/j.fusengdes.2010.09.009

• Neutronics
• CTF
• Spherical tokamak
• Fusion

One of the crucial aspects of fusion research is the optimisation and qualification of suitable materials and components. To enable the design and construction of DEMO in the future, ITER is taken to demonstrate the scientific and technological feasibility and IFMIF will provide rigorous testing of small material samples. Meanwhile, a dedicated, small-scale components testing facility (CTF) is proposed to complement and extend the functions of ITER and IFMIF and operate in association with DEMO so as to reduce the risk of delays during this phase of fusion power development. The design of a spherical tokamak (ST)-based CTF is being developed which offers many advantages over conventional machines, including lower tritium consumption, easier maintenance, and a compact assembly. The neutronics analysis of this system is presented here.
Based on a three-dimensional neutronics model generated by the interface programme MCAM from CAD models, a series of nuclear and radiation protection analyses were carried out using the MCNP code and FENDL2.1 nuclear data library to assess the current design and guide its development if needed. The nuclear analyses addresses key neutronics issues such as the neutron wall loading (NWL) profile, nuclear heat loads, and radiation damage to the coil insulation and to structural components, particularly the stainless steel vessel wall close to the NBI ports where shielding is limited. The shielding of the divertor coil and the internal Poloidal Field (PF) coil, which is introduced in the expanded divertor design, are optimised to reduce their radiation damage. The preliminary results show that the peak radiation damage to the structure of martensitic/ferritic steel is about 29 dpa at the mid-plane assuming a life of 12 years at a duty factor 33%, which is much lower than its similar to 150 dpa limit. In addition, TBMs installed in 8 mid-plane ports and 6 lower ports, and 60% Li-6 enrichment in the Li4SiO4 breeder, the total tritium generation is similar to 3.7 kg in the whole lifetime of CTF.

• 出版日期2010-12