聚变堆中子倍增剂Be中的杂质活化对其多次回收利用的影响分析

Activation Analysis of the Impacts of Impurities in Irradiated Beryllium for Recycling and Reuse in Fusion Reactors

回收和重新利用聚变堆中的放射性物质以避免或减少地表掩埋需求的管理策略已经成为国际聚变堆放废研究的一大趋势。在固态包层被辐照后,中子倍增剂铍(Be)的回收利用具有重要的价值。本文分析了 Be 中的杂质在多次回收利用的辐照循环中的活化对其回收利用的影响。计算结果表明经过 10~20 次的回收利用后,Be 的活度已经接近活化最大值。只有回收操作的接触剂量率限值在 1 Sv/h 量级以上时,才能在停堆冷却数十年内实现 Be 的回收利用。

Recycling and reuse of radioactive materials in fusion reactors to avoid or reduce the need of land burial disposal has been a trend in the international fusion radwaste management research. Recycling and reuse of the irradiated neutron multiplier of beryllium would be of great value. In this contribution,the activation of beryllium in multiple irradiation cycles was performed,and the impacts of the impurities on the recycling and reuse of beryllium were analyzed. The results showed that the activation of beryllium was close to its maximum value after 10 to 20 irradiation cycles. Recycling of beryllium could be achieved within tens of years of cooling after shutdown only when the acceptance criterion for contact dose rate was above 1 Sv/h of magnitude level.