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

Journal Article · Sat Nov 28 00:00:00 EST 2015 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2015.11.005· OSTI ID:1249213

Pawelko, R. J. ^[1]; Shimada, M. ^[1]; Katayama, K. ^[2]; Fukada, S. ^[2]; Humrickhouse, P. W. ^[1]; Terai, T. ^[3]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
2. Kyushu Univ., Fukuoka (Japan)
3. The Univ. of Tokyo, Tokyo (Japan)

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 of a surface-limited regime.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC07-05ID14517
• OSTI ID: 1249213
• Alternate ID(s): OSTI ID: 1397325
• Report Number(s): INL/JOU-15-34193; PII: S0920379615303306
• Journal Information: Fusion Engineering and Design, Vol. 102, Issue C; ISSN 0920-3796
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
tritium
permeation
lead lithium eutectic
mass transfer properties