8–12 Jun 2026
Karlsruhe Institute of Technology, Campus north
Europe/Berlin timezone

Comparative Analysis of Activated Corrosion Products in Key Systems of a Burning Plasma Experimental Tokamak

8 Jun 2026, 17:00
1h
FTU (Karlsruhe Institute of Technology, Campus north)

FTU

Karlsruhe Institute of Technology, Campus north

Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen
Poster Activation-related issues Poster Session

Speaker

Chen Yang (Institute of Energy, Hefei Comprehensive National Science Center)

Description

Activated corrosion products (ACPs) are a key source term for shutdown dose rates and radioactive waste management in fusion reactors. In this paper, we focus on a burning plasma experimental tokamak and apply the CATE (Corrosion, Activation and Transport Evaluation) code to analyze four key systems: blanket first wall, shield block, vacuum vessel, and divertor. We calculate the evolution of ACPs during pulsed operation (0–10 years) and the post-shutdown period (10–40 years), examine the influence of coolant water chemistry, and track changes in main radionuclides. Our results show that immediately after shutdown, the blanket first wall exhibits the highest activity, followed by the shield block and the divertor, while the vacuum vessel shows the lowest. During the post-shutdown period, activity in all systems decays over time, but the blanket first wall remains the highest throughout. Increasing the coolant pH generally reduces the production of ACPs. The main radionuclides in the coolant evolve in distinct stages: during early operation, Cu-64, Cr-51, and Fe-55 prevail; at later cooling times, long lived nuclides such as Ni-63, Fe-55, and Co-60 become dominant. This work provides a quantitative basis for source term control and personnel protection in fusion reactors.

Formatted abstract uploaded? Done.

Author

Chen Yang (Institute of Energy, Hefei Comprehensive National Science Center)

Presentation materials