2023 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[1A07-11] Divertor and Superconducting Materials

Mon. Mar 13, 2023 2:45 PM - 4:10 PM Room A (11 Bildg.1F 1101)

Chair:satoshi konishi(Kyoto Fusioneering)

3:15 PM - 3:30 PM

[1A09] Strain reduction in tungsten due to annealing and change in hydrogen isotope permeation behavior.

*Hiroki Yata1, Kobayashi Makoto1,2, Takuya Nagasaka1,2 (1. The Graduate University for Advanced Studies, 2. National Institute for Fusion Science)

Keywords:hydrogen isotopes, permeation, tungsten

In D-T fusion power plants, the accumulation of hydrogen isotopes in the reactor materials leads to the loss of tritium, which is the fuel for fusion, and also affects the materials performance. The purpose of this study was to clarify the relationship between the strain in tungsten and the hydrogen isotopes trapped in the strain by investigating the change in hydrogen isotope permeation behavior when tungsten foils are annealed.