低レベル放射性廃棄物浅地中埋設におけるコンクリートピットのバリア性能
1990 年 25 巻 2 号 p. 107-114
詳細
1990 年 25 巻 2 号 p. 107-114
Performance of a concrete vault as an engineered barrier for low-level radioactive wastes was studied. For this purpose, 137Cs solution was stored in the concrete vault for approximately 600 days and the activity profile of 137Cs was measured. The profile was explained by diffusion mechanism and the apparent diffusion coefficients of 137Cs in concrete were calculated. The results suggest that there are two processes in the diffusion in concrete. The diffusion from the surface and that from the solution. The calculated apparent diffusion coefficients for each process are 1.7×10-14m2/s and 1.7×10-13m2/s respectively. Furthermore, no big difference was seen in the values for the carbonated concrete, therefore, long term barrier performance of the concrete vault is expected.
