Clarification of tritium behavior in pbli blanket system

S. Fukada, T. Terai, S. Konishi, K. Katayama, T. Chikada, Y. Edao, T. Muroga, M. Shimada, B. Merrill, D. K. Sze

研究成果: Contribution to journalReview article査読

7 被引用数 (Scopus)

抄録

In order to clarify the tritium behavior in PbLi blanket system, the solubility of hydrogen isotopes in the PbLi eutectic alloy was experimentally investigated. The effects of (i Li preferential evaporation from PbLi, (ii) thermal convection in a quartz-glass reaction tube and (iii) difference in crucible materials between A22O3 and W on the solubilities were discussed. Another important issue of the PbLi blanket system is to develop a new ceramic coating to decrease tritium permeation rate. Tritium permeation test was performed for Er2O3 coating on F82H. The permeation reduction factor achieved here was higher than 103. Precise experiments were carried out to determine the solubility, diffusivity and permeability of hydrogen isotopes in PbLi eutectic alloy by means of a transient permeation method. The isotope effects in solubility and diffusivity between H and D were clarified. No isotope effect in solubility was observed between H and D, and the H diffusivity was 1.4 times larger than the D one. The ratio was near to a value predicted from the classical theory. Experiment using tritium is designed under the collaboration work with INL.

本文言語英語
ページ(範囲)425-429
ページ数5
ジャーナルMaterials Transactions
54
4
DOI
出版ステータス出版済み - 2013

All Science Journal Classification (ASJC) codes

  • 材料科学(全般)
  • 凝縮系物理学
  • 材料力学
  • 機械工学

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