Tritium inventory in the ITER PFC's: Predictions, uncertainties, R&D status and priority needs
Tritium inventory in the ITER PFC's: Predictions, uncertainties, R&D status and priority needs
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DOI：
10.1016/s0920-3796(98)00151-3
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发表时间：
1998-09
影响因子：
1.7
通讯作者：
G. Federici;R. Anderl;J. Brooks;R. Causey;J. P. Coad;D. Cowgill;R. Doerner;A. A. Haasz-A.;G. Longhurst;S. Luckhardt;D. Mueller;A. Peacock;M. Pick;C. Skinner;W. Wampler;K. Wilson;C. Wong;C. Wu;D. Youchison
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文献类型：
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作者：
G. Federici;R. Anderl;J. Brooks;R. Causey;J. P. Coad;D. Cowgill;R. Doerner;A. A. Haasz-A.;G. Longhurst;S. Luckhardt;D. Mueller;A. Peacock;M. Pick;C. Skinner;W. Wampler;K. Wilson;C. Wong;C. Wu;D. Youchison
目前，在与国际热核聚变实验反应堆（ITER）中预期的条件类似的条件下，各种实验室正在提供关于铍和钨中氢等离子体同位素保留的新数据，而以前的数据要么缺失，要么基本上分散。随着认识的重大进步，有必要重新审视以前对热核实验堆氚存量的估计，铍作为第一壁部件的等离子体面对材料，钨在偏滤器中，靠近撞击点有一些碳纤维复合材料包层区域。基于这些分析，它表明，主要关注的领域，相对于氚库存，仍然与碳和可能的铍偏滤器表面上的共沉积。在这里，ITER偏滤器条件的建模继续显示出潜在的大共沉积率，这是托卡马克研究结果所证实的。与存在于大部分材料深处的氚相反，这种表面氚代表了一种安全危险，因为它在发生事故时很容易被调动。但是，它可以被移除和恢复。它的结论是，积极和有效的方法来消除共沉积层需要在ITER和定期调节/清洗将需要控制氚库存，避免耗尽可用的燃料供应。结合推断其适用于ITER所需的研究和开发工作，简要讨论了一些可能用于原位清洗的方法。
New data on hydrogen plasma isotopes retention in beryllium and tungsten are now becoming available from various laboratories for conditions similar to those expected in the International Thermonuclear Experimental Reactor (ITER) where previous data were either missing or largely scattered. Together with a significant advancement in understanding, they have warranted a revisitation of the previous estimates of tritium inventory in ITER, with beryllium as the plasma facing material for the first-wall components, and tungsten in the divertor with some carbon-fibre-composites clad areas, near the strike points. Based on these analyses, it is shown that the area of primary concern, with respect to tritium inventory, remains codeposition with carbon and possibly beryllium on the divertor surfaces. Here, modelling of ITER divertor conditions continues to show potentially large codeposition rates which are confirmed by tokamak findings. Contrary to the tritium residing deep in the bulk of materials, this surface tritium represents a safety hazard as it can be easily mobilised in the event of an accident. It could, however, be possibly removed and recovered. It is concluded that active and efficient methods to remove the codeposited layers are needed in ITER and periodic conditioning/cleaning would be required to control the tritium inventory and avoid exhausting the available fuel supply. Some methods which could possibly be used for in-situ cleaning are briefly discussed in conjunction with the research and development work required to extrapolate their applicability to ITER.