Damage behavior of He-irradiated sintered SiC at high temperatures
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21230%2F25%3A00383321" target="_blank" >RIV/68407700:21230/25:00383321 - isvavai.cz</a>
Result on the web
<a href="https://doi.org/10.1016/j.jnucmat.2025.155839" target="_blank" >https://doi.org/10.1016/j.jnucmat.2025.155839</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.jnucmat.2025.155839" target="_blank" >10.1016/j.jnucmat.2025.155839</a>
Alternative languages
Result language
angličtina
Original language name
Damage behavior of He-irradiated sintered SiC at high temperatures
Original language description
Understanding the effects of high-temperature helium (He) irradiation on the damage behavior of sintered silicon carbide (SiC) is crucial for assessing the material's stability in advanced nuclear reactors. In this study, we investigate the impact of 230 keV He ions on SiC at temperatures of 800 °C and 1000 °C, utilizing three different irradiation fluences: 2 x 1016/cm2, 4 x 1016/cm2, and 1.6 x 1017/cm2. Raman spectroscopy and transmission electron microscopy were employed to analyze various damage features, including irradiation-induced lattice strain, platelet formation, dislocation loops, and helium bubbles. Our findings indicate that over-pressurized platelets predominantly formed on the (0001) plane, with a limited number of dislocation loops detected nearby. In contrast, numerous black spot defects were observed near grain boundaries, where platelets were absent. This variation in defect distribution underscores the unique damage behavior associated with high-temperature He irradiation. The insights gained from this study are essential for understanding the structural changes and integrity of SiC materials under conditions relevant to nuclear reactor applications.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20504 - Ceramics
Result continuities
Project
<a href="/en/project/EH22_008%2F0004590" target="_blank" >EH22_008/0004590: Robotics and advanced industrial production</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2025
Confidentiality
C - Předmět řešení projektu podléhá obchodnímu tajemství (§ 504 Občanského zákoníku), ale název projektu, cíle projektu a u ukončeného nebo zastaveného projektu zhodnocení výsledku řešení projektu (údaje P03, P04, P15, P19, P29, PN8) dodané do CEP, jsou upraveny tak, aby byly zveřejnitelné.
Data specific for result type
Name of the periodical
Journal of Nuclear Materials
ISSN
0022-3115
e-ISSN
1873-4820
Volume of the periodical
612
Issue of the periodical within the volume
June
Country of publishing house
NL - THE KINGDOM OF THE NETHERLANDS
Number of pages
9
Pages from-to
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UT code for WoS article
001477764600001
EID of the result in the Scopus database
2-s2.0-105003197970