Institute of Physics Publishing Plasma Physics and Controlled Fusion Tritium Retention in next Step Devices and the Requirements for Mitigation and Removal Techniques
Institute of Physics Publishing Plasma Physics and Controlled Fusion Tritium Retention in next Step Devices and the Requirements for Mitigation and Removal Techniques
复制标题
DOI：
--
复制
发表时间：
--
期刊：
影响因子：
--
通讯作者：
G. Counsell;P. Coad;C. Grisola;C. Hopf;W. Jacob;A. Kirschner;A. Kreter;K. Krieger;J. Likonen;V. Philipps;J. Roth;M. Rubel;E. Salançon;A. Semerok;F. Tabares;A. Widdowson;J. Efda
中科院分区：
文献类型：
--
作者：
G. Counsell;P. Coad;C. Grisola;C. Hopf;W. Jacob;A. Kirschner;A. Kreter;K. Krieger;J. Likonen;V. Philipps;J. Roth;M. Rubel;E. Salançon;A. Semerok;F. Tabares;A. Widdowson;J. Efda
在托卡马克与碳等离子体面对组件的燃料物种的保留机制，连同估计相应的保留氚在ITER。相应的要求，新的和改进的计划，以减少氚库存的突出和正在进行的研究到一系列技术的结果，连同估计的氚去除率在热核实验堆在每种情况下。最后，提出了一种方法，涉及到许多氚去除技术集成到热核实验堆的运行时间表，作为一种手段，以延长操作期间之前，需要进行重大干预。
Mechanisms underlying the retention of fuel species in tokamaks with carbon plasma-facing components are presented, together with estimates for the corresponding retention of tritium in ITER. The consequential requirement for new and improved schemes to reduce the tritium inventory is highlighted and the results of ongoing studies into a range of techniques are presented, together with estimates of the tritium removal rate in ITER in each case. Finally, an approach involving the integration of many tritium removal techniques into the ITER operational schedule is proposed as a means to extend the period of operations before major intervention is required.