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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

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • 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

  • UT code for WoS article

    001477764600001

  • EID of the result in the Scopus database

    2-s2.0-105003197970