Effects of Dual-Ion Irradiation on the Swelling of SiC/SiC Composites

Kishimoto, Hirotatsu; Ozawa, Kazumi; Kondo, Sosuke

doi:10.2320/matertrans.46.1923

Cited by 14 publications

(3 citation statements)

References 14 publications

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“…In graphite, swelling is actually negative for moderate neutron irradiation doses in the range of 400-900°C [23,24], but extrapolation of published data indicates that graphite swelling should be positive for high dose, low temperature irradiations such as the 300°C test discussed here. Similarly, swelling has been observed in pyrolytic carbon with a turbostratic structure [25].…”

Section: Resultsmentioning

confidence: 61%

High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations

Perez-Bergquist

Nozawa

Shih

et al. 2015

Journal of Nuclear Materials

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h i g h l i g h t sHi-Nicalon SiC fiber composites were neutron irradiated to >70 dpa at 300-800°C. Minimal changes were observed in samples irradiated at 800°C. 300°C samples exhibited substantial microstructural changes in interphase layers. Growth of and phase changes in carbonaceous particles in the fibers were observed. a b s t r a c tOver the past decade, significant progress has been made in the development of silicon carbide (SiC) composites, composed of near-stoichiometric SiC fibers embedded in a crystalline SiC matrix, to the point that such materials can now be considered nuclear grade. Recent neutron irradiation studies of Hi-Nicalon Type S SiC composites showed excellent radiation response at damage levels of 30-40 dpa at temperatures of 300-800°C. However, more recent studies of these same fiber composites irradiated to damage levels of >70 dpa at similar temperatures showed a marked decrease in ultimate flexural strength, particularly at 300°C. Here, electron microscopy is used to analyze the microstructural evolution of these irradiated composites in order to investigate the cause of the degradation. While minimal changes were observed in Hi-Nicalon Type S SiC composites irradiated at 800°C, substantial microstructural evolution is observed in those irradiated at 300°C. Specifically, carbonaceous particles in the fibers grew by 25% compared to the virgin case, and severe cracking occurred at interphase layers.

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Section: Resultsmentioning

confidence: 61%

High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations

Perez-Bergquist

Nozawa

Shih

et al. 2015

Journal of Nuclear Materials

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“…The latest neutronics work by Sawan et al [75] predicts the production rates of 50 -180 appm He/dpa and 20 -70 appm H/dpa for gaseous transmutations and 10 -45 appm Mg/dpa, 5 -18 appm Be/dpa, 3 -14 appm Al/dpa, and 0.2 -1.5 appm P/dpa, depending on the blanket concept and magnetic or inertial confinement, for the most notable solid transmutations. The high production rate for helium is known to cause enhanced swelling due like to stability of the interstitial helium [76] at intermediate temperatures during ion irradiation [77] and through stabilization of vacancy clusters at high temperatures (>~1000°C)…”

Section: Transmutation Effectsmentioning

confidence: 99%

Current status and recent research achievements in SiC/SiC composites

Katoh

Snead

Henager

et al. 2014

Journal of Nuclear Materials

311

120

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The development and maturation of the silicon carbide fiber-reinforced silicon carbide matrix (SiC/SiC) composite system for fusion applications has seen the evolution from fundamental development and understanding of the material system and its behavior in a hostile irradiation environment to the current effort which essentially is a broad-based program of technology, directed at moving this material class from a laboratory curiosity to an engineering material. This paper lays out the recent international scientific and technological achievements in the development of SiC/SiC composite material technologies for fusion application and will discuss future research directions. It also reviews the materials system in the larger context of progress to maturity as an engineering material for both the larger nuclear community and for general engineering applications.

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“…It was found that SiC f /SiC experiences moderate swelling, which saturates above 1-dpa irradiation at around 2% and below 1% at 300 • C and 800 • C, respectively [30]. A study on the synergic effect of He on microstructural development of irradiated SiC f /SiC composite showed that the swelling was marginally larger than 1% (approximately 1.5%), but that up to 1000 • C, there was no void swelling [33], [34], [35]. Swelling is thus expected to be less significant at the proposed operating temperature of the SCYLLA© blanket.…”

Section: A Sic F /Sicmentioning

confidence: 99%

Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

Pearson¹,

Baus²,

Konishi³

et al. 2022

IEEE Trans. Plasma Sci.

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This article outlines Kyoto Fusioneering's (KF's) initial engineering and development activities for its self-cooled lithium lead-type blanket: Self-Cooled Yuryo Lithium-Lead Advanced (SCYLLA©). We provide details on overall design, including an initial tritium breeding ratio (TBR) assessment via neutronics analysis, as well as the status of SCYLLA©-relevant R&D. This includes silicon carbide composite (SiC f /SiC) manufacturing techniques, tritium extraction, materials compatibility, and heat transfer, which are being explored via collaboration with Kyoto University. Results of previous work in relation to this R&D are presented. Permeability coefficients indicate a promising property of SiC f /SiC tritium hermeticity at high temperatures. Tritium extraction technology via vacuum sieve tray (VST) is shown to be demonstrated at engineering scale. A local TBR of up to 1.4 can be achieved with the SCYLLA© configuration. Fabrication methods for various SiC f /SiC components including the blanket module, heat exchanger, and flow path components are provided. A tritium compatible high-temperature SiC f /SiC heat exchanger is discussed. Commercial viability and reactor adaptability are considered as a theme throughout. Finally, KF's plans to build a facility for demonstration reactor relevant testing of a SCYLLA© prototype in the mid-2020s, which will provide a significant step toward commercial fusion energy, are presented.

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Effects of Dual-Ion Irradiation on the Swelling of SiC/SiC Composites

Cited by 14 publications

References 14 publications

High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations

High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations

Current status and recent research achievements in SiC/SiC composites

Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

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