Presentation Information
[3H13]Evaluation of Tritium and Carbon-14 Migration and Diffusion Behavior in Damaged Nuclear Structural Materials
*Shingo Okumura1, Ayumu Hayakawa1, Yuzuka Hoshino1, Makoto Kobayashi2, Takuji Oda3, Yasuhisa Oya1 (1. Shizuoka Univ., 2. NIFS, 3. Seoul Natl. Univ.)
Keywords:
Surface analysis,Irradiation defect,Nuclear structural material,Tritium
For the decommissioning of nuclear facilities, simple and quick decontamination/stabilization of radionuclides in/on nuclear structural materials are required. The difficulties are that these materials are damaged by high-density neutron irradiation, and mobile radionuclides such as tritium and carbon-14 are easily trapped by the irradiation defects. We have analyzed the chemical states and depth profiles of deuterium and carbon for the unirradiated samples of SS316L and Zircalloy-2. In this study, we will discuss the chemical states and depth profiles for the damaged samples with different irradiation doses introduced near the surface by energetic Fe2+ irradiation and aim to experimentally elucidate the role of irradiation defects on the migration and diffusion mechanisms of deuterium and carbon in nuclear structure materials.