Silicon Carbide as a tritium permeation barrier in tungsten plasma-facing components

Wright, G. M.; Durrett, M. G.; Hoover, K. W.; Kesler, L. A.; Whyte, D. G.

doi:10.1016/j.jnucmat.2014.12.074

Silicon Carbide as a tritium permeation barrier in tungsten plasma-facing components

Journal Article · Tue Dec 23 00:00:00 EST 2014 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2014.12.074· OSTI ID:1897973

Wright, G. M. ^[1]; Durrett, M. G. ^[2]; Hoover, K. W. ^[2]; Kesler, L. A. ^[3]; Whyte, D. G. ^[3]

Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center; OSTI
Nanohmics Inc., Austin, TX (United States)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center

The control of tritium inventory is of great importance in future fusion reactors, not only from a safety standpoint but also to maximize a reactor’s efficiency. Due to the high mobility of hydrogenic species in tungsten (W) one concern is the loss of tritium from the system via permeation through the tungsten plasma-facing components (PFC). This can lead to loss of tritium through the cooling channels of the wall thereby mandating tritium monitoring and recovery methods for the cooling system of the first wall. The permeated tritium is then out of the fuel cycle and cannot contribute to energy production until it is recovered and recycled into the system. Most work on tritium permeation barriers has been focused at the breeding blanket where tritium is bred to maintain a self-sustaining tritium fuel cycle. Tritium inventory control is critical there as well to maintain a viable tritium breeding ratio, but there is also a great benefit to reducing permeation of tritium through the PFC (e.g. the first wall). This stems from the fact that the rate at which the tritium recycles between the plasma and solute state in the plasma-facing materials is much larger than any other tritium “loop” in the reactor. Here, this work demonstrates that a thin layer of silicon carbide (SiC) can be used in a W PFC to greatly reduce hydrogenic permeation while maintaining structural integrity of the PFC through rapid thermal anneal and thermal cycling tests up to 1023 K.

Research Organization:: Nanohmics Inc., Austin, TX (United States)

Sponsoring Organization:: USDOE; USDOE Office of Science (SC), Engineering & Technology. Office of Small Business Innovation Research (SBIR) and Small Business Technology Transfer (STTR) Programs

Grant/Contract Number:: SC0009685

OSTI ID:: 1897973

Alternate ID(s):: OSTI ID: 1252354

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 458; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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