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In situ study of thermal shock damage to high-temperature ceramics. / Cherepanov, D. E.; Vyacheslavov, L. N.; Popov, V. A. et al.

In: Nuclear Materials and Energy, Vol. 36, 101495, 09.2023.

Research output: Contribution to journal › Article › peer-review

Harvard

Cherepanov, DE, Vyacheslavov, LN, Popov, VA, Ryzhkov, GA, Kasatov, AA, Vasilyev, AA, Arakcheev, AS, Ruktuev, AA, Kandaurov, IV & Shoshin, AA 2023, 'In situ study of thermal shock damage to high-temperature ceramics', Nuclear Materials and Energy, vol. 36, 101495. https://doi.org/10.1016/j.nme.2023.101495

APA

Cherepanov, D. E., Vyacheslavov, L. N., Popov, V. A., Ryzhkov, G. A., Kasatov, A. A., Vasilyev, A. A., Arakcheev, A. S., Ruktuev, A. A., Kandaurov, I. V., & Shoshin, A. A. (2023). In situ study of thermal shock damage to high-temperature ceramics. Nuclear Materials and Energy, 36, [101495]. https://doi.org/10.1016/j.nme.2023.101495

Vancouver

Cherepanov DE, Vyacheslavov LN, Popov VA, Ryzhkov GA, Kasatov AA, Vasilyev AA et al. In situ study of thermal shock damage to high-temperature ceramics. Nuclear Materials and Energy. 2023 Sept;36:101495. doi: 10.1016/j.nme.2023.101495

Author

Cherepanov, D. E. ; Vyacheslavov, L. N. ; Popov, V. A. et al. / In situ study of thermal shock damage to high-temperature ceramics. In: Nuclear Materials and Energy. 2023 ; Vol. 36.

BibTeX

@article{862c4f37bc144fdcbe806ab5a04c3ef0,
title = "In situ study of thermal shock damage to high-temperature ceramics",
abstract = "New generations of fusion devices need alternative plasma-facing materials. The currently approved material composition for the first wall and divertor of the ITER tokamak has a number of disadvantages: insufficient resistance to thermal shock, sputtering of microparticles into plasma and high atomic number Z of the armor material. A promising but largely untested idea is the proposal to use high-temperature ceramics as armor materials for the most heat-loaded plasma-facing components of new-generation fusion devices. Among the advantages of ceramics are the low Z and high enough resistance to intense heating. More research is needed that would help to understand how the material withstands high heat fluxes during transient plasma events. This work is devoted to the description of an experimental method that makes it possible to estimate the critical temperature at which the damage of ceramics begins as a result of a thermal shock of submillisecond duration. As a demonstration of the efficiency of the method, the critical temperature for hot pressed B4C under thermal shock was determined: its value was about 1200–1400 K.",
keywords = "Boron carbide, High-temperature ceramics, In situ diagnostics, Laser heating, Plasma-facing components, Thermal shock",
author = "Cherepanov, {D. E.} and Vyacheslavov, {L. N.} and Popov, {V. A.} and Ryzhkov, {G. A.} and Kasatov, {A. A.} and Vasilyev, {A. A.} and Arakcheev, {A. S.} and Ruktuev, {A. A.} and Kandaurov, {I. V.} and Shoshin, {A. A.}",
year = "2023",
month = sep,
doi = "10.1016/j.nme.2023.101495",
language = "English",
volume = "36",
journal = "Nuclear Materials and Energy",
issn = "2352-1791",
publisher = "Elsevier Ltd",

}

RIS

TY - JOUR

T1 - In situ study of thermal shock damage to high-temperature ceramics

AU - Cherepanov, D. E.

AU - Vyacheslavov, L. N.

AU - Popov, V. A.

AU - Ryzhkov, G. A.

AU - Kasatov, A. A.

AU - Vasilyev, A. A.

AU - Arakcheev, A. S.

AU - Ruktuev, A. A.

AU - Kandaurov, I. V.

AU - Shoshin, A. A.

PY - 2023/9

Y1 - 2023/9

N2 - New generations of fusion devices need alternative plasma-facing materials. The currently approved material composition for the first wall and divertor of the ITER tokamak has a number of disadvantages: insufficient resistance to thermal shock, sputtering of microparticles into plasma and high atomic number Z of the armor material. A promising but largely untested idea is the proposal to use high-temperature ceramics as armor materials for the most heat-loaded plasma-facing components of new-generation fusion devices. Among the advantages of ceramics are the low Z and high enough resistance to intense heating. More research is needed that would help to understand how the material withstands high heat fluxes during transient plasma events. This work is devoted to the description of an experimental method that makes it possible to estimate the critical temperature at which the damage of ceramics begins as a result of a thermal shock of submillisecond duration. As a demonstration of the efficiency of the method, the critical temperature for hot pressed B4C under thermal shock was determined: its value was about 1200–1400 K.

AB - New generations of fusion devices need alternative plasma-facing materials. The currently approved material composition for the first wall and divertor of the ITER tokamak has a number of disadvantages: insufficient resistance to thermal shock, sputtering of microparticles into plasma and high atomic number Z of the armor material. A promising but largely untested idea is the proposal to use high-temperature ceramics as armor materials for the most heat-loaded plasma-facing components of new-generation fusion devices. Among the advantages of ceramics are the low Z and high enough resistance to intense heating. More research is needed that would help to understand how the material withstands high heat fluxes during transient plasma events. This work is devoted to the description of an experimental method that makes it possible to estimate the critical temperature at which the damage of ceramics begins as a result of a thermal shock of submillisecond duration. As a demonstration of the efficiency of the method, the critical temperature for hot pressed B4C under thermal shock was determined: its value was about 1200–1400 K.

KW - Boron carbide

KW - High-temperature ceramics

KW - In situ diagnostics

KW - Laser heating

KW - Plasma-facing components

KW - Thermal shock

UR - https://www.scopus.com/record/display.uri?eid=2-s2.0-85170435076&origin=inward&txGid=e6524667b55d711e20c7daec2500ecbd

UR - https://www.mendeley.com/catalogue/3b47494f-ab85-3812-a090-98162b5c3b50/

U2 - 10.1016/j.nme.2023.101495

DO - 10.1016/j.nme.2023.101495

M3 - Article

VL - 36

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

SN - 2352-1791

M1 - 101495

ER -

ID: 55508861