TY - JOUR
T1 - Evaluation of tritium confinement performance of the assembly composed of zirconium and alumina simulating lithium rod
AU - Henzan, Daisuke
AU - Katayama, Kazunari
AU - Matsuura, Hideaki
N1 - Funding Information:
We would like to appreciate Dr. Makoto Oya and Dr. Toshiharu Takeishi in Kyushu University, and Dr. Teppei Otsuka in Kindai University for their comments on the experiments, analysis, and discussion of this study. This work was supported by JSPS KAKENHI Grant-in-Aid for Scientific Research (B)JP18H01200 and Research(B) JP19H01877.
Publisher Copyright:
© 2021
Copyright:
Copyright 2021 Elsevier B.V., All rights reserved.
PY - 2021/7
Y1 - 2021/7
N2 - 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.
AB - 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.
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U2 - 10.1016/j.fusengdes.2021.112372
DO - 10.1016/j.fusengdes.2021.112372
M3 - Article
AN - SCOPUS:85102351941
SN - 0920-3796
VL - 168
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
M1 - 112372
ER -