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Recent advances and issues in development of silicon carbide composites for fusion applications

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TLDR
In this paper, the effects of high-temperature neutron irradiation on microstructural evolution, thermal and electrical conductivities and mechanical properties including the fiber/matrix interfacial strength are specified under various irradiation conditions.
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This article is published in Journal of Nuclear Materials.The article was published on 2009-04-30. It has received 130 citations till now. The article focuses on the topics: Silicon carbide & Ceramic.

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Blanket/first wall challenges and required R&D on the pathway to DEMO

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.
Journal ArticleDOI

Silicon carbide composites as fusion power reactor structural materials

TL;DR: 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.
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MAX phase carbides and nitrides: Properties for future nuclear power plant in-core applications and neutron transmutation analysis

TL;DR: In this paper, the specific activities of ternary carbides and nitrides, known as MAX phases, combine attractive properties of both ceramics and metals, and has been suggested for potential nuclear reactor applications.
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Microencapsulated fuel technology for commercial light water and advanced reactor application

TL;DR: The potential application of microencapsulated fuels to light water reactors (LWRs) has been explored in this paper, where the specific fuel manifestation being put forward is for coated fuel particles embedded in silicon carbide or zirconium metal matrices.
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Opportunities for Advanced Ceramics and Composites in the Nuclear Sector

TL;DR: Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides as mentioned in this paper.
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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Current status and critical issues for development of SiC composites for fusion applications

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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Promise and challenges of SiCf/SiC composites for fusion energy applications

TL;DR: In this article, the authors have made advances in understanding radiation damage in SiC at the fundamental level through MD simulations of displacement cascades and showed that SiC composites made with the advanced fibers of Nicalon Type S and the UBE Tyranno SA have excellent thermal conductivity and radiation stability.
Journal ArticleDOI

Properties of silicon carbide for nuclear fuel particle coatings

R. J. Price
- 01 Sep 1977 - 
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.
Journal ArticleDOI

Microstructural development in cubic silicon carbide during irradiation at elevated temperatures

TL;DR: In this article, the development of chemically vapor-deposited (CVD) high-purity beta-SiC during neutron and self-ion irradiation at elevated temperatures was studied.
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