Critical issues and current status of SiC/SiC composites for fusion

Hasegawa, Akira; Jones, Russell H.; Snead, Lance Lewis; Riccardi, B.; Fenici, P.

doi:10.1016/s0022-3115(00)00374-3

Cited by 170 publications

(86 citation statements)

References 39 publications

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“…For over a decade nuclear programs have followed the research carried out under such programs as the DOE Continuous Fiber Ceramic Composite and Fossil Energy programs as well as the work by NASA and others toward the development of SiC fiber, SiC matrix composites. While the issues for nuclear application of SiC are somewhat different than these non-nuclear programs, the potential benefit of the composites are the same [1][2][3][4][5][6]. By incorporation of continuous fibers into SiC, cracks that would otherwise propagate and cause catastrophic failure are tied-up at the fiber/matrix interface.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of neutron irradiated silicon carbide and silicon carbide composites

Newsome

Snead

Hinoki

et al. 2007

Journal of Nuclear Materials

142

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The effects of fast neutron irradiation on SiC and SiC composites have been studied. The materials used were chemical vapor deposition (CVD) SiC and SiC/SiC composites reinforced with either Hi-Nicalon™ Type-S, Hi-Nicalon™ or Sylramic™ fibers fabricated by chemical vapor infiltration. Statistically significant numbers of flexural samples were irradiated up to 4.6 x 10 25 n/m 2 (E>0.1 MeV) at 300, 500 and 800°C in the High Flux Isotope Reactor at Oak Ridge National Laboratory. Dimensions and weights of the flexural bars were measured before and after the neutron irradiation. Mechanical properties were evaluated by four point flexural testing.Volume increase was seen for all bend bars following neutron irradiation. Magnitude of swelling depended on irradiation temperature and material, while it was nearly independent of irradiation fluence over the fluence range studied. Flexural strength of CVD SiC increased following irradiation depending on irradiation temperature. Over the temperature range studied, no significant degradation in mechanical properties was seen for composites fabricated with Hi-Nicalon™ Type-S, while composites reinforced with Hi-Nicalon™ or Sylramic fibers showed significant degradation. The effects of irradiation on the Weibull failure statistics are also presented suggesting a reduction in the Weibull modulus upon irradiation. The cause of this potential reduction is not known.

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Section: Introductionmentioning

confidence: 99%

Evaluation of neutron irradiated silicon carbide and silicon carbide composites

Newsome

Snead

Hinoki

et al. 2007

Journal of Nuclear Materials

142

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“…These bubbles preferentially occupy highvolume [14] or high-energy locations, including interfaces [15]. Understanding the physical mechanisms of interaction between He bubbles and interfaces may shed light on the design of radiation-resistant materials for advanced fission [16] and future fusion [17] reactors.…”

Section: Introductionmentioning

confidence: 99%

Imaging the in-plane distribution of helium precipitates at a Cu/V interface

Chen

Yuryev

et al. 2017

Materials Research Letters

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We describe a transmission electron microscopy investigation of the distribution of helium precipitates within the plane of an interface between Cu and V. Statistical analysis of precipitate locations reveals a weak tendency for interfacial precipitates to align along 110 -type crystallographic directions within the Cu layer. Comparison of these findings with helium-free Cu/V interfaces suggests that the precipitates may be aggregating preferentially along atomic-size steps in the interface created by threading dislocations in the Cu layer. Our observations also suggest that some precipitates may be aggregating along intersections between interfacial misfit dislocations. IMPACT STATEMENTThe innovation of this paper is providing the first plane-view experimental images of in-plane helium precipitate distributions at an interface between physical vapor deposited face-centered cubic (fcc) and body-centered cubic (bcc) metals. ARTICLE HISTORY

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“…Chemically vapor deposited (CVD) SiC has been used as a pressure vessel material for the tristructural-isotropic fuel particles for high temperature gas-cooled reactors and novel accident tolerant fuel concepts for light water reactors [2]. The use of SiC/SiC composites as the structural materials has also been proposed in various advanced fission reactor concepts and fusion reactors [3] [4]. Driven by the need to increase the safety margins of nuclear reactors in accident scenarios, the research and development of accident-tolerant fuel has become important in the nuclear engineering and materials community.…”

Section: Introductionmentioning

confidence: 99%

Positron annihilation spectroscopy investigation of vacancy defects in neutron-irradiated3C-SiC

Koyanagi

Katoh

et al. 2017

Phys. Rev. B

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Abstract:Positron annihilation spectroscopy characterization results for neutron-irradiated 3C-SiC are described here, with a specific focus on explaining the size and character of vacancy clusters as a complement to the current understanding of the neutron irradiation response of 3C-SiC. Positron annihilation lifetime spectroscopy was used to capture the irradiation temperature and dose dependence of vacancy defects in 3C-SiC following neutron irradiation from 0.01 to 31 dpa in the temperature range from 380 to 790°C. The neutral and negatively charged vacancy clusters were identified and quantified. The results suggest that the vacancy defects that were measured by positron annihilation spectroscopy technique contribute very little to the transient swelling of SiC. In addition, coincidence Doppler broadening measurement was used to investigate the chemical identity surrounding the positron trapping sites. It was found that silicon vacancy-related defects dominate in the studied materials and the production of the antisite defect C Si may result in an increase in the probability of positron annihilation with silicon core electrons.

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Critical issues and current status of SiC/SiC composites for fusion

Cited by 170 publications

References 39 publications

Evaluation of neutron irradiated silicon carbide and silicon carbide composites

Evaluation of neutron irradiated silicon carbide and silicon carbide composites

Imaging the in-plane distribution of helium precipitates at a Cu/V interface

Positron annihilation spectroscopy investigation of vacancy defects in neutron-irradiated3C-SiC

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