Silicon Carbide as a tritium permeation barrier in tungsten plasma-facing components
Abstract
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 themore »
- Authors:
-
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
- Nanohmics Inc., Austin, TX (United States)
- Publication Date:
- Research Org.:
- Nanohmics, Inc., Austin, TX (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Engineering & Technology. Office of Small Business Innovation Research (SBIR) and Small Business Technology Transfer (STTR) Programs
- OSTI Identifier:
- 1897973
- Alternate Identifier(s):
- OSTI ID: 1252354
- Grant/Contract Number:
- SC0009685
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 458; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Citation Formats
Wright, G. M., Durrett, M. G., Hoover, K. W., Kesler, L. A., and Whyte, D. G. Silicon Carbide as a tritium permeation barrier in tungsten plasma-facing components. United States: N. p., 2014.
Web. doi:10.1016/j.jnucmat.2014.12.074.
Wright, G. M., Durrett, M. G., Hoover, K. W., Kesler, L. A., & Whyte, D. G. Silicon Carbide as a tritium permeation barrier in tungsten plasma-facing components. United States. https://doi.org/10.1016/j.jnucmat.2014.12.074
Wright, G. M., Durrett, M. G., Hoover, K. W., Kesler, L. A., and Whyte, D. G. Tue .
"Silicon Carbide as a tritium permeation barrier in tungsten plasma-facing components". United States. https://doi.org/10.1016/j.jnucmat.2014.12.074. https://www.osti.gov/servlets/purl/1897973.
@article{osti_1897973,
title = {Silicon Carbide as a tritium permeation barrier in tungsten plasma-facing components},
author = {Wright, G. M. and Durrett, M. G. and Hoover, K. W. and Kesler, L. A. and Whyte, D. G.},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2014.12.074},
journal = {Journal of Nuclear Materials},
number = ,
volume = 458,
place = {United States},
year = {Tue Dec 23 00:00:00 EST 2014},
month = {Tue Dec 23 00:00:00 EST 2014}
}
Free Publicly Available Full Text
Publisher's Version of Record
Other availability
Search WorldCat to find libraries that may hold this journal
Cited by: 9 works
Citation information provided by
Web of Science
Web of Science
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.
Works referenced in this record:
Deuterium permeation behavior of erbium oxide coating on austenitic, ferritic, and ferritic/martensitic steels
journal, June 2009
- Chikada, Takumi; Suzuki, Akihiro; Yao, Zhenyu
- Fusion Engineering and Design, Vol. 84, Issue 2-6
Thermal conductivity in hot-pressed silicon carbide
journal, January 1996
- Liu, Dean-Mo; Lin, Bor-Wen
- Ceramics International, Vol. 22, Issue 5
Deuterium transport in SiCf/SiC composites
journal, December 2002
- Esteban, G. A.; Perujo, A.; Legarda, F.
- Journal of Nuclear Materials, Vol. 307-311
Thermal expansion of tungsten
journal, December 1925
- Hidnert, P.; Sweeney, W. T.
- Scientific Papers of the Bureau of Standards, Vol. 20
Tritium migration in vapor-deposited β-silicon carbide
journal, September 1993
- Causey, R. A.; Wampler, W. R.; Retelle, J. R.
- Journal of Nuclear Materials, Vol. 203, Issue 3
Summary Abstract: Permeation of hydrogen through CVD silicon carbide
journal, April 1984
- Sinharoy, S.; Lange, W. J.
- Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, Vol. 2, Issue 2
Depth profiling of deuterium implanted into stainless steel at room temperature
journal, February 1978
- Altstetter, C. J.; Behrisch, R.; Bøttiger, J.
- Nuclear Instruments and Methods, Vol. 149, Issue 1-3
Deuterium permeation and thermal behaviors of amorphous silicon carbide coatings on steels
journal, October 2011
- Chikada, Takumi; Suzuki, Akihiro; Terai, Takayuki
- Fusion Engineering and Design, Vol. 86, Issue 9-11
Simultaneous irradiation effects of hydrogen and helium ions on tungsten
journal, April 2009
- Ueda, Y.; Fukumoto, M.; Yoshida, J.
- Journal of Nuclear Materials, Vol. 386-388
Thermal Conductivity of Pure and Impure Silicon, Silicon Carbide, and Diamond
journal, December 1964
- Slack, Glen A.
- Journal of Applied Physics, Vol. 35, Issue 12
Hydrogen Diffusion and Solubility in Silicon Carbide
journal, May 1978
- Causey, R. A.; Fowler, J. D.; Ravanbakht, Camran
- Journal of the American Ceramic Society, Vol. 61, Issue 5-6
Solution and Diffusion of Hydrogen in Tungsten
journal, May 1969
- Frauenfelder, R.
- Journal of Vacuum Science and Technology, Vol. 6, Issue 3
Thermal conductivity of liquid phase sintered silicon carbide
journal, June 2003
- Sigl, L. S.
- Journal of the European Ceramic Society, Vol. 23, Issue 7
Fabrication of ZrO2coatings on ferritic steel by wet-chemical methods as a tritium permeation barrier
journal, December 2011
- Hatano, Y.; Zhang, K.; Hashizume, K.
- Physica Scripta, Vol. T145
Works referencing / citing this record:
Effect of Nitrogen Doping and Temperature on Mechanical Durability of Silicon Carbide Thin Films
journal, July 2018
- Tomastik, Jan; Ctvrtlik, Radim; Ingr, Tomas
- Scientific Reports, Vol. 8, Issue 1