Zobrazeno 1 - 10
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pro vyhledávání: '"I.J. van Rooyen"'
Akademický článek
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Autor:
Al-Amin Ahmed Simon, Lyle Jones, Bahareh Badamchi, Maria Mitkova, I.J. van Rooyen, Harish Subbaraman, Yoshifumi Sakaguchi, H. Kunold
Publikováno v:
Scientific Reports
Scientific Reports, Vol 11, Iss 1, Pp 1-15 (2021)
Scientific Reports, Vol 11, Iss 1, Pp 1-15 (2021)
Chalcogenide glasses are one of the most versatile materials that have been widely researched because of their flexible optical, chemical, electronic, and phase change properties. Their application is usually in the form of thin films, which work as
Publikováno v:
Journal of Nuclear Materials. 512:252-267
The Transient Reactor Test (TREAT) facility resides at the Materials and Fuels Complex (MFC) at Idaho National Laboratory (INL). The TREAT reactor is currently undergoing design and engineering studies for its conversion from a high enriched uranium
Akademický článek
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Akademický článek
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Publikováno v:
Journal of Materials Processing Technology. 241:73-85
Resumption of operations at the Transient Reactor Test (TREAT) facility at Idaho National Laboratory was approved in 2014 to meet U.S. Department of Energy Office of Nuclear Energy objectives in transient testing of nuclear fuels. In parallel, the Na
Publikováno v:
Journal of Nuclear Materials. 476:93-101
Electron microscopy investigations of selected coated particles from the first advanced gas reactor experiment at Idaho National Laboratory provided important information on fission product distribution and chemical composition in the silicon-carbide
Publikováno v:
Nuclear Engineering and Design. 305:277-283
Precession electron diffraction (PED), a transmission electron microscopy-based technique, has been evaluated for the suitability for evaluating grain boundary character in the SiC layer of tristructural isotropic (TRISO) fuel. This work reports the
Publikováno v:
Journal of Nuclear Materials. 475:62-70
Historic and recent post-irradiation-examination from the German AVR and Advanced Gas Reactor Fuel Development and Qualification Project have shown that 110 m Ag is released from intact tristructural isotropic (TRISO) fuel. Although TRISO fuel partic
Autor:
I.J. van Rooyen, T.M. Lillo
Publikováno v:
Journal of Nuclear Materials. 473:83-92
In this study, the fission product precipitates at silicon carbide grain boundaries from an irradiated TRISO particle were identified and correlated with the associated grain boundary characteristics. Precession electron diffraction in the transmissi