Tritium fuel cycle in ITER and DEMO: Issues in handling large amount of fuel
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  • 作者:T. Tanabe tanabe@nucl.kyushu-u.ac.jp
  • 刊名:Journal of Nuclear Materials
  • 出版年:2013
  • 出版时间:July, 2013
  • 年:2013
  • 卷:438
  • 期:supp_S
  • 页码:S19-S26
  • 全文大小:1559 K
文摘
Since tritium resources are very limited, economical conversion of fusion energy to electricity and/or heat must have an enough margin to keep self-fuel-sufficiency and simultaneously ensure tritium safety. To realize this, tritium inventory in reactor systems, which use ¡«1017 Bq (a few kg) of tritium, should be kept as small as possible, under strict accountancy or regulation of a few tens Bq (¡«pg). In present tokamaks, however, hydrogen retention rate is significantly large, i.e. more than 5 % of fueled hydrogen is continuously piled up in their vacuum vessels, which must not be allowed in a reactor. Moreover, both fuelling and burning efficiencies are very poor, only a few % or less. Accordingly, huge amount of tritium fuel must be recycled.

In the paper, after the introduction of tritium as a hydrogen radioisotope, important issues to establish safe and economical tritium fuel cycle for a fusion reactor will be summarized considering the handling of large amounts of tritium, i.e. confinement, leakage, contamination, permeation, regulation and tritium accountancy.

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