Low tritium partial pressure permeation system for mass transport measurement in lead lithium eutectic

R. J. Pawelko, M. Shimada, K. Katayama, S. Fukada, P. W. Humrickhouse, T. Terai

研究成果: Contribution to journalArticle査読

8 被引用数 (Scopus)

抄録

This paper describes a new experimental system designed to investigate tritium mass transfer properties in materials important to fusion technology. Experimental activities were carried out at the Safety and Tritium Applied Research (STAR) facility located at the Idaho National Laboratory (INL). The tritium permeation measurement system was developed as part of the Japan/US TITAN collaboration to investigate tritium mass transfer properties in liquid lead lithium eutectic (LLE) alloy. The experimental system is configured to measure tritium mass transfer properties at low tritium partial pressures. Initial tritium permeation scoping tests were conducted on a 1 mm thick α-Fe plate to determine operating parameters and to validate the experimental technique. A second series of permeation tests was then conducted with the α-Fe plate covered with an approximately 8.5 mm layer of liquid lead lithium eutectic alloy (α-Fe/LLE). We present preliminary tritium permeation data for α-Fe and α-Fe/LLE at temperatures between 400 and 600 °C and at tritium partial pressures between 1.7E - 03 and 2.5 Pa in helium. Preliminary results for the α-Fe plate and α-Fe/LLE indicate that the data spans a transition region between the diffusion-limited regime and the surface-limited regime. Additional data is required to determine the existence and range of a surface-limited regime.

本文言語英語
ページ(範囲)8-13
ページ数6
ジャーナルFusion Engineering and Design
102
DOI
出版ステータス出版済み - 1 1 2016

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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