[2C01-06] Heat- and Mass-Transfer Characteristic, Engineering Design

[2C01] Development of a simulation code for the transports of heat, tritium and irradiation defects through interfaces in solid

*Makoto Kobayashi¹, Masanori Hara², Yasuhisa Oya³, Masashi Shimada⁴, Chase Tayler⁴ (1. National Institute for Fusion Science, 2. The University of Toyama, 3. Shizuoka University, 4. Idaho National Laboratory)

Keywords:Tritium, Tungsten, neutron, Vacancy

Tritium tranpsort such as retention, diffusion, in the first wall of fusion reactor is influenced by the irradiation defects induced by neutron, and has the temperature dependency on its kinetics. In this work, the simulation code for the transport kinetics of heat, tritium and irradiation defects in the system with temperaure gradient and interfaces was developed.