Tritium retention in graphite inner wall of JT-60U
Tritium retention in graphite inner wall of JT-60U
复制标题
JT-60U石墨内壁氚滞留
DOI：
10.1016/0920-3796(95)00431-9
复制
发表时间：
1996
影响因子：
1.7
通讯作者：
K. Okuno
中科院分区：
文献类型：
--
作者：
K. Masaki;K. Kodama;T. Ando;M. Saidoh;M. Shimizu;T. Hayashi;K. Okuno
自1991年7月以来，在JT-60U上进行了D-D实验。虽然由D-D反应产生的氚被编程为通过泵送系统排出，但一部分氚被捕获在石墨内壁中。为了评价JT-60U石墨壁中氚的滞留情况，1993年11月从JT-60U上取下了几块样品瓦。用燃烧样品片、氚转化为HTO和闪烁计数生成水的方法测定了石墨砖中氚的分布。测量结果表明，在石墨第一壁中仍有1.6 × 10~（10）Bq的氚残留。这一数值相当于1991年7月至1993年10月JT-60U产生的氚的约50%。偏滤器瓦中的氚浓度高于第一壁中的氚浓度。特别是，氚浓度在撞击点之间的瓦片中达到峰值。在电子或离子直接撞击的撞击点处，氚浓度较低。
In JT-60U, D-D experiments have been performed since July 1991. Although tritium, which is produced by the D-D reaction, is programmed to be exhausted through pumping systems, a part of the tritium is trapped in the graphite inner wall. To evaluate the tritium retention in the graphite wall of JT-60U, several sample tiles were removed from JT-60U in November 1993. The retained tritium distribution in the graphite tiles was measured by means of burning sample pieces, converting the tritium into HTO and scintillation counting the resultant water. The result of this measurement showed that tritium of 1.6 × 1010Bq still remained in the graphite first wall. This value corresponds to approximately 50% of the tritium generated from July 1991 to October 1993 in JT-60U. The tritium remaining in the divertor tiles was in higher concentration than that in the first wall. In particular, the tritium concentration peaked in the tiles between the strike points. Tritium at the strike points, where an electron or ion strikes directly, was in low concentration.