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Title: Recent progress in the development of SiC composites for nuclear fusion applications

Abstract

Silicon carbide (SiC) fiber reinforced SiC matrix composites continue to undergo development for fusion applications worldwide because of inherent advantages of the material including low activation, high temperature capability, relatively low neutron absorption, and radiation resistance. This work presents an international overview of recent achievements in SiC-based composites for fusion applications. Key subjects include applications in fusion reactors, high-dose radiation effects, transmutation effects, material lifetime assessment, and development of joining technology (processing, test method development, irradiation resistance, and modeling capability). This paper also discusses synergy among research for fusion materials and non-fusion materials (for fission and aerospace applications). Finally, future research directions and opportunities are proposed.

Authors:
ORCiD logo [1]; ORCiD logo [1];  [2];  [3]; ORCiD logo [4]; ORCiD logo [5];  [6];  [7];  [8]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. National Institutes for Quantum and Radiological Science and Technology, Aomori (Japan)
  3. Stony Brook Univ., Stony Brook, NY (United States)
  4. Tohoku Univ., Sendai (Japan)
  5. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
  6. Politecnico di Torino, Torino (Italy)
  7. Kyoto Univ., Kyoto (Japan)
  8. Chinese Academy of Sciences, Zhejiang (China)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1479787
Alternate Identifier(s):
OSTI ID: 1457746
Report Number(s):
PNNL-SA-130414
Journal ID: ISSN 0022-3115
Grant/Contract Number:  
AC05-00OR22725; AC05-76RL01830
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 511; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats

Koyanagi, Takaaki, Katoh, Yutai, Nozawa, Takashi, Snead, Lance L., Kondo, Sosuke, Henager, Jr., Charles H., Ferraris, Monica, Hinoki, Tatsuya, and Huang, Qing. Recent progress in the development of SiC composites for nuclear fusion applications. United States: N. p., 2018. Web. https://doi.org/10.1016/j.jnucmat.2018.06.017.
Koyanagi, Takaaki, Katoh, Yutai, Nozawa, Takashi, Snead, Lance L., Kondo, Sosuke, Henager, Jr., Charles H., Ferraris, Monica, Hinoki, Tatsuya, & Huang, Qing. Recent progress in the development of SiC composites for nuclear fusion applications. United States. https://doi.org/10.1016/j.jnucmat.2018.06.017
Koyanagi, Takaaki, Katoh, Yutai, Nozawa, Takashi, Snead, Lance L., Kondo, Sosuke, Henager, Jr., Charles H., Ferraris, Monica, Hinoki, Tatsuya, and Huang, Qing. Thu . "Recent progress in the development of SiC composites for nuclear fusion applications". United States. https://doi.org/10.1016/j.jnucmat.2018.06.017. https://www.osti.gov/servlets/purl/1479787.
@article{osti_1479787,
title = {Recent progress in the development of SiC composites for nuclear fusion applications},
author = {Koyanagi, Takaaki and Katoh, Yutai and Nozawa, Takashi and Snead, Lance L. and Kondo, Sosuke and Henager, Jr., Charles H. and Ferraris, Monica and Hinoki, Tatsuya and Huang, Qing},
abstractNote = {Silicon carbide (SiC) fiber reinforced SiC matrix composites continue to undergo development for fusion applications worldwide because of inherent advantages of the material including low activation, high temperature capability, relatively low neutron absorption, and radiation resistance. This work presents an international overview of recent achievements in SiC-based composites for fusion applications. Key subjects include applications in fusion reactors, high-dose radiation effects, transmutation effects, material lifetime assessment, and development of joining technology (processing, test method development, irradiation resistance, and modeling capability). This paper also discusses synergy among research for fusion materials and non-fusion materials (for fission and aerospace applications). Finally, future research directions and opportunities are proposed.},
doi = {10.1016/j.jnucmat.2018.06.017},
journal = {Journal of Nuclear Materials},
number = C,
volume = 511,
place = {United States},
year = {2018},
month = {6}
}

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Figures / Tables:

Figure 1 Figure 1: Simulated temperature distribution in a tungsten monoblock with SiC/SiC composite coolant duct. The impinging heat load on the upper surface is 7.6 MW/m2. The image was reprinted from [10].

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Works referencing / citing this record:

High-Temperature Creep Properties of SiC Fibers with Different Compositions
journal, August 2019


Interfacial optimization of SiC nanocomposites reinforced by SiC nanowires with high volume fraction
journal, March 2019

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