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

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-3 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. In conclusion, additional data is required to determine the existence and range ofmore » a surface-limited regime.« less
 [1] ;  [1] ;  [2] ;  [2] ;  [1] ;  [3]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Kyushu Univ., Fukuoka (Japan)
  3. The Univ. of Tokyo, Tokyo (Japan)
Publication Date:
Report Number(s):
Journal ID: ISSN 0920-3796; PII: S0920379615303306
Grant/Contract Number:
Accepted Manuscript
Journal Name:
Fusion Engineering and Design
Additional Journal Information:
Journal Volume: 102; Journal Issue: C; Journal ID: ISSN 0920-3796
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
Country of Publication:
United States
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; tritium; permeation; lead lithium eutectic; mass transfer properties
OSTI Identifier:
Alternate Identifier(s):
OSTI ID: 1397325