Evaluation of tritium confinement performance of the assembly composed of zirconium and alumina simulating lithium rod

研究成果: Contribution to journalArticle査読

1 被引用数 (Scopus)

抄録

A high temperature gas cooled reactor is proposed as an external tritium source for stably starting up of fusion reactors. A Li rod coated with zirconium and alumina have been proposed to confine produced tritium. Although the tritium leakage from the Li rod has been estimated by the simulation, it is necessary to evaluate the tritium confinement performance experimentally. In this study, the test assembly simulating the Li rod composed of Inner Zr tube - Outer Zr tube - Al2O3 tube was built up, and tritium confinement experiments were conducted. The test assembly successfully confined tritium, which was contained in the Ar gas mainly as HTO and slightly as HT, for 12 h and 87 h at a high temperature of 700 °C. It was suggested that an oxide layer formed on the Zr tube contributed to suppress tritium permeation in HTO.

本文言語英語
論文番号112372
ジャーナルFusion Engineering and Design
168
DOI
出版ステータス出版済み - 7 2021

All Science Journal Classification (ASJC) codes

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学

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