Tritium release behavior from steels irradiated by high energy protons

H. Nakamura, K. Kobayashi, T. Yamanishi, S. Yokoyama, S. Saito, K. Kikuchi

研究成果: Article査読

2 被引用数 (Scopus)


Thermal desorption behavior of tritium has been investigated for SS316 and F82H irradiated by 580MeV proton (SINQ-target3) up to 5.0 -5.9 dpa and 6.3-9.1 dpa, respectively, in order to understand tritium transport in the irradiated materials. While the tritium release has only one peak at 670 K from irradiated SS316, that has two peaks at 510 K and 670 K from irradiated F82H. Those results indicate that only one kind of trap site exists in the SS316, and at least two kinds of trap site exist in F82H. As the results of tritium transport analysis of tritium release behavior, it was found that the trap site at 670 K for SS316 and F82H could be controlled by the same trap mechanism. As to the chemical form of tritium released from the steels, 1/2 and 1/3 of tritium was release as water vapor form from SS316 and F82H, respectively. It could be attributed to the growth of surface oxide on the metal surfaces during the TDS.

ジャーナルFusion Science and Technology
出版ステータスPublished - 01-01-2007

All Science Journal Classification (ASJC) codes

  • 土木構造工学
  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学


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