Compatibility of FeCrAlMo with flowing PbLi at 500°-650 °C

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Abstract

To explore the upper temperature limit of a fusion blanket utilizing eutectic Pb-17at.%Li for tritium breeding, a series of three mono-metallic thermal convection loops have been fabricated from alloy APMT (Fe–21Cr–5Al–3Mo) and operated with commercial PbLi and increasing peak temperatures of 550°, 600° and 650 °C, flow rates of 0.4–0.7 cm/s and temperature gradients of 85–115 °C. Chains of APMT specimens including 25 mm long tensile specimens were hung in the hot and cold legs of the loops to evaluate post-exposure room temperature tensile properties after 1000 h exposures in each experiment. For specimens exposed to flowing PbLi above 500 °C, only minor changes in tensile properties were observed after exposure. Most APMT specimens were pre-oxidized to form alumina prior to exposure and exhibited small mass losses as the alumina was partially transformed to α-LiAlO2 that tended to spall after exposure. Specimens without pre-oxidation exhibited higher mass losses and formed γ-LiAlO2 but with less spallation. While promising for increasing blanket temperatures, the small mass losses suggest that the surface oxide is not completely stable. However, even at the highest temperatures, there was no indication of classic dissolution/precipitation behavior suggesting that higher temperature compatibility may be possible.

Original languageEnglish
Article number151847
JournalJournal of Nuclear Materials
Volume528
DOIs
StatePublished - Jan 2020

Funding

The research was funded by the Office of Fusion Energy Sciences, U.S. Department of Energy . Sandvik provided some of the APMT material used in these experiments. The experimental work at ORNL was assisted by A. Willoughby, E. Cakmak, M. Stephens, T. Lowe, T. Jordan, C. Stevens and D. Coffey. Helpful suggestions were provided by F. W. Wiffen, P. F. Tortorelli, S. J. Pawel, M. Romedenne and T. R. Watkins. The TEM work was supported by the U.S. Department of Energy, Office of Nuclear Energy, Fuel Cycle R&D Program and the Nuclear Science User Facilities . The research was funded by the Office of Fusion Energy Sciences, U.S. Department of Energy. Sandvik provided some of the APMT material used in these experiments. The experimental work at ORNL was assisted by A. Willoughby, E. Cakmak, M. Stephens, T. Lowe, T. Jordan, C. Stevens and D. Coffey. Helpful suggestions were provided by F. W. Wiffen, P. F. Tortorelli, S. J. Pawel, M. Romedenne and T. R. Watkins. The TEM work was supported by the U.S. Department of Energy, Office of Nuclear Energy, Fuel Cycle R&D Program and the Nuclear Science User Facilities.

FundersFunder number
Nuclear Science User Facilities
Office of Fusion Energy Sciences
U.S. Department of Energy
Office of Nuclear Energy
Oak Ridge National Laboratory
The Ministry of Economic Affairs and Employment

    Keywords

    • FeCrAlMo
    • Fusion blanket
    • Liquid metal compatibility
    • Pb–Li

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