Journal ArticleDOI
Silicon carbide composites as fusion power reactor structural materials
Lance Lewis Snead,Takashi Nozawa,Monica Ferraris,Yutai Katoh,Robert J. Shinavski,Mohamed E. Sawan +5 more
TLDR
The recent progress in the understanding and of basic phenomenon related to the use of SiC and SiC composite in fusion applications will be presented in this article, including both fundamental radiation effects in SiC, and engineering issues such as joining and general materials properties.About:
This article is published in Journal of Nuclear Materials.The article was published on 2011-10-01. It has received 222 citations till now. The article focuses on the topics: Silicon carbide.read more
Citations
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Journal ArticleDOI
Designing Radiation Resistance in Materials for Fusion Energy
TL;DR: In this article, three fundamental options for designing radiation resistance are outlined: Utilize matrix phases with inherent radiation tolerance, select materials in which vacancies are immobile at the design operating temperatures, or engineer materials with high sink densities for point defect recombination.
Journal ArticleDOI
Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects
Yutai Katoh,Kazumi Ozawa,Chunghao Shih,Takashi Nozawa,Robert J. Shinavski,Akira Hasegawa,Lance Lewis Snead +6 more
TL;DR: In this article, a summary of the properties of SiC/SiC composites with chemically vapor-infiltrated (CVI) SiC matrices is presented.
Journal ArticleDOI
Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation
TL;DR: In this paper, a single phase (face centered cubic) concentrated solid solution alloy of composition 27%Fe-28%Ni-27%Mn-18%Cr was irradiated with 3 or 5.8 MeV Ni ions at temperatures ranging from room temperature to 700 Ã 0.03 to 10 displacements per atom (dpa).
Journal ArticleDOI
Current status and recent research achievements in SiC/SiC composites
Yutai Katoh,Lance Lewis Snead,Charles H. Henager,Takashi Nozawa,Tatsuya Hinoki,Aljaž Iveković,Saša Novak,S.M. González de Vicente +7 more
TL;DR: The silicon carbide fiber-reinforced SiC/SiC composite system for fusion applications has seen a continual evolution from development a fundamental understanding of the material system and its behavior in a hostile irradiation environment to the current effort which is directed at a broad-based program of technology maturation program as mentioned in this paper.
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Blanket/first wall challenges and required R&D on the pathway to DEMO
Mohamed A. Abdou,Neil B. Morley,Sergey Smolentsev,Alice Ying,Siegfried Malang,Arthur Rowcliffe,M.A. Ulrickson +6 more
TL;DR: In this paper, the authors summarized the top technical issues and elucidates the primary challenges in developing the blanket/first wall and identified the key R&D needs in non-fusion and fusion facilities on the path to DEMO.
References
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Journal ArticleDOI
Handbook of SiC properties for fuel performance modeling
TL;DR: In this paper, a compilation of non-irradiated and irradiated properties of SiC are provided and reviewed and analyzed in terms of application to TRISO fuels, specifically in the high-temperature irradiation regime.
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High-strength alkali-resistant sintered SiC fibre stable to 2,200 °C
TL;DR: In this article, a type of silicon carbide fiber obtained by sintering an amorphous Si-Al-C-O fibre precursor at 1,800°C was described.
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Current status and critical issues for development of SiC composites for fusion applications
Yutai Katoh,Lance Lewis Snead,Charles H. Henager,Akira Hasegawa,Akira Kohyama,B. Riccardi,Hans Hegeman +6 more
TL;DR: In this paper, the authors review the development, characterization, and irradiation effect studies for SiC composites for fusion energy applications and make the case that SiC composite are progressing from the stage of potential viability and proof-of-principle to one where they are ready for system demonstration, i.e., for flow channel inserts in Pb-Li blankets.
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Properties of silicon carbide for nuclear fuel particle coatings
TL;DR: The properties of pyrolytic silicon carbide (SiC) that are important to its use in nuclear fuel particle coatings are reviewed in this paper, where the structure of material deposited under different conditions varies.
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Ceramic materials for fusion
L. H. Rovner,G. R. Hopkins +1 more
TL;DR: In this paper, a range of property values that are useful for evaluating range of applicability of low-atom ceramics materials is presented, including carbon, SiC, Be2C, B4C, TiC, Al2O3, and BeO.