2022年春の年会

講演情報

一般セッション

VI. 核融合工学 » 601-3 トリチウム工学(燃料回収・精製,計測,同位体効果,安全取扱い)

[2L08-12] トリチウム工学

2022年3月17日(木) 14:45 〜 16:15 L会場

座長:大矢 恭久 (静岡大)

15:30 〜 15:45

[2L11] Tritium distribution in Be limiter tiles used in JET ITER-like wall experiments

*Sun Eui Lee1, Yuji Hatano1, Yasuhisa Oya2, Suguru Masuzaki3, Masayuki Tokitani3, Mitsutaka Miyamoto4, Nobuyuki Asakura5, Hirofumi Nakamura5, Yasunori Iwai5, Takumi Hayashi5 (1. Univ. of Toyama, 2. Shizuoka Univ., 3. NIFS, 4. Shimane University, 5. QST)

キーワード:JET-ILW, DT fusion reaction, DD fusion reaction, high energy triton, co-deposition, thermal energy desorption

Tritium (T) distributions in Be limiter tiles used in 1st, 3rd or 1st-3rd JET ITER-like wall experimental campaign were examined. Outer poloidal limiter showed the highest T content and it increased with increasing plasma exposure time. On the other hand, T content in the upper or inner limiters were low and showed no systematic correlation with plasma exposure time. These results indicated that the inner and upper tiles were more affected by heat load from the plasma.