[3H09-14] Decommissioning Technologies in General

3:45 PM - 4:00 PM JST(6:45 AM - 7:00 AM UTC)

[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.