High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces

Nozawa, Takashi; Koyanagi, Takaaki; Katoh, Yutai; Tanigawa, Hiroyasu

doi:10.1016/j.jeurceramsoc.2019.03.014

Title: High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces

Full Record
Other Related Research

Abstract

SiC/SiC composites are promising structural candidate materials for various nuclear applications over the wide temperature range of 300–1000 °C. Accordingly, irradiation tolerance over this wide temperature range needs to be understood to ensure the performance of these composites. In this study, neutron irradiation effects on dimensional stability and mechanical properties to high doses (11–44 dpa) at intermediate irradiation temperatures (˜600 °C) were evaluated for Hi-Nicalon Type-S or Tyranno-SA3 fiber–reinforced SiC matrix composites produced by chemical vapor infiltration. The influence of various fiber/matrix interfaces, such as a 50–120 nm thick pyrolytic carbon (PyC) monolayer interphase and 70–130 nm thick PyC with a subsequent PyC (˜20 nm)/SiC (˜100 nm) multilayer, was evaluated and compared with the previous results for a thin-layer PyC (˜20 nm)/SiC (˜100 nm) multilayer interphase. Four-point flexural tests were conducted to evaluate post-irradiation strength, and SEM and TEM were used to investigate microstructure. Regardless of the fiber type, monolayer composites showed considerable reduction of flexural properties after irradiation to 11–12 dpa at 450–500 °C; and neither type showed the deterioration identified at the same dose level at higher temperatures (>750 °C) in a previous study. After further irradiation to 44 dpa at 590–640 °C, the degradation was enhanced comparedmore »« less

Authors:

Nozawa, Takashi ^[1];

^[2];

^[2]; Tanigawa, Hiroyasu ^[1]

National Institutes for Quantum and Radiological Science and Technology (QST), Aomori (Japan)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: Thu Mar 07 00:00:00 EST 2019

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1504005

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Journal of the European Ceramic Society

Additional Journal Information:: Journal Volume: 39; Journal Issue: 8; Journal ID: ISSN 0955-2219

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE; Silicon carbide fiber-reinforced silicon carbide matrix composites; Neutron irradiation; Intermediate temperature; Fiber/matrix interface; Flexural properties

Citation Formats


                    Nozawa, Takashi, Koyanagi, Takaaki, Katoh, Yutai, and Tanigawa, Hiroyasu. High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces.  United States: N. p., 2019. 
Web.  doi:10.1016/j.jeurceramsoc.2019.03.014.

Copy to clipboard


                    Nozawa, Takashi, Koyanagi, Takaaki, Katoh, Yutai, & Tanigawa, Hiroyasu. High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces.  United States.  https://doi.org/10.1016/j.jeurceramsoc.2019.03.014

Copy to clipboard


                    Nozawa, Takashi, Koyanagi, Takaaki, Katoh, Yutai, and Tanigawa, Hiroyasu. Thu .  
"High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces".  United States.  https://doi.org/10.1016/j.jeurceramsoc.2019.03.014.  https://www.osti.gov/servlets/purl/1504005.

Copy to clipboard


                    
@article{osti_1504005,

  title        = {High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces},

  author       = {Nozawa, Takashi and Koyanagi, Takaaki and Katoh, Yutai and Tanigawa, Hiroyasu},

  abstractNote = {SiC/SiC composites are promising structural candidate materials for various nuclear applications over the wide temperature range of 300–1000 °C. Accordingly, irradiation tolerance over this wide temperature range needs to be understood to ensure the performance of these composites. In this study, neutron irradiation effects on dimensional stability and mechanical properties to high doses (11–44 dpa) at intermediate irradiation temperatures (˜600 °C) were evaluated for Hi-Nicalon Type-S or Tyranno-SA3 fiber–reinforced SiC matrix composites produced by chemical vapor infiltration. The influence of various fiber/matrix interfaces, such as a 50–120 nm thick pyrolytic carbon (PyC) monolayer interphase and 70–130 nm thick PyC with a subsequent PyC (˜20 nm)/SiC (˜100 nm) multilayer, was evaluated and compared with the previous results for a thin-layer PyC (˜20 nm)/SiC (˜100 nm) multilayer interphase. Four-point flexural tests were conducted to evaluate post-irradiation strength, and SEM and TEM were used to investigate microstructure. Regardless of the fiber type, monolayer composites showed considerable reduction of flexural properties after irradiation to 11–12 dpa at 450–500 °C; and neither type showed the deterioration identified at the same dose level at higher temperatures (>750 °C) in a previous study. After further irradiation to 44 dpa at 590–640 °C, the degradation was enhanced compared with conventional multilayer composites with a PyC thickness of ˜20 nm. Multilayer composites have shown comparatively good strength retention for irradiation to ˜40 dpa, with moderate mechanical property degradation beginning at 70–100 dpa. As a result, irradiation-induced debonding at the F/M interface was found to be the major cause of deterioration of various composites.},

  doi          = {10.1016/j.jeurceramsoc.2019.03.014},

  journal      = {Journal of the European Ceramic Society},

  number       = 8,

  volume       = 39,

  place        = {United States},

  year         = {Thu Mar 07 00:00:00 EST 2019},

  month        = {Thu Mar 07 00:00:00 EST 2019}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.jeurceramsoc.2019.03.014

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 11 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions

Journal Article Koyanagi, Takaaki ; Katoh, Yutai - Journal of Nuclear Materials

Silicon carbide (SiC) fiber–reinforced SiC matrix (SiC/SiC) composites are being actively investigated for use in accident-tolerant core structures of light water reactors (LWRs). Owing to the limited number of irradiation studies previously conducted at LWR-coolant temperature, this paper examined SiC/SiC composites following neutron irradiation at 230–340 °C to 2.0 and 11.8 dpa in the High Flux Isotope Reactor. The investigated materials were chemical vapor infiltrated (CVI) SiC/SiC composites with three different reinforcement fibers. The fiber materials were monolayer pyrolytic carbon (PyC) -coated Hi-Nicalon™ Type-S (HNS), Tyranno™ SA3 (SA3), and SCS-Ultra™ (SCS) SiC fibers. The irradiation resistance of these composites wasmore »« less
Cited by 32
https://doi.org/10.1016/j.jnucmat.2017.07.007

Full Text Available
PIE of nuclear grade SiC/SiC flexural coupons irradiated to 10 dpa at LWR temperature

Technical Report Koyanagi, Takaaki ; Katoh, Yutai

Silicon carbide fiber-reinforced SiC matrix (SiC/SiC) composites are being actively investigated for accident-tolerant core structures of light water reactors (LWRs). Owing to the limited number of irradiation studies previously conducted at LWR-coolant temperature, this study examined SiC/SiC composites following neutron irradiation at 230–340°C to 2.0 and 11.8 dpa in the High Flux Isotope Reactor. The investigated materials are chemical vapor infiltrated (CVI) SiC/SiC composites with three different reinforcement fibers. The fiber materials were monolayer pyrolytic carbon (PyC)-coated Hi-NicalonTM Type-S (HNS), TyrannoTM SA3 (SA3), and SCS-Ultra^TM (SCS) SiC fibers. The irradiation resistance of these composites was investigated based on flexural behavior,more »« less
https://doi.org/10.2172/1360077

Full Text Available
Fiber/matrix debonding evaluation of SiCf/SiC composites using micropillar compression technique

Journal Article Karakoc, Omer ; Koyanagi, Takaaki ; Nozawa, Takashi ; ... - Composites Part B: Engineering

Third-generation silicon carbide (SiC) composites reinforced by SiC fibers (Hi-Nicalon S [HNS] and Tyranno SA3 [SA3]) are attractive for use in next generation reactors owing to their high strength and chemical inertness at high temperatures, as well as enhanced radiation tolerance under neutron irradiation environments. To optimize composite performance, the interfacial mechanical properties of chemical vapor–infiltrated (CVI) SiC_f/SiC composites are investigated in this effort by using a slant interface micropillar compression testing procedure. The micropillar test specimens, containing an inclined pyrolytic carbon (PyC) interphase, are prepared using a focused ion beam. The novel microcompression testing successfully quantifies the debond shearmore »« less
https://doi.org/10.1016/j.compositesb.2021.109189

Full Text Available
Failure evaluation of neutron-irradiated SiC/SiC composites by underwater acoustic emission

Journal Article Nozawa, Takashi ; Koyanagi, Takaaki ; Katoh, Yutai ; ... - Journal of Nuclear Materials

Here, understanding the statistical properties of mechanical properties of non-irradiated and neutron-irradiated SiC/SiC composites is essential for component design. This study aims to evaluate the detailed damage accumulation behavior of composites focusing on two fracture parameters: proportional limit stress (PLS) and acoustic emission (AE) onset stress. The developmental underwater AE technique, which is benefit in non-contact in-situ failure monitoring method during mechanical testing and in handle of the irradiated material, was first applied to evaluate damage accumulation behavior. Two types of chemical vapor infiltration SiC/SiC composites were used: one reinforced with Hi-Nicalon Type-S SiC fiber and one reinforced with Tyranno-SA3more »« less
https://doi.org/10.1016/j.jnucmat.2022.153787

Full Text Available
The effects of neutron irradiation on shear properties at the monolayered PyC and the multilayered PyC/SiC interfaces of SiC/SiC composites

Journal Article Nozawa, Takashi ; Katoh, Yutai ; Snead, Lance Lewis - Journal of Nuclear Materials

The effect of neutron irradiation on mechanical properties at the fiber/matrix interface of SiC/SiC composites was evaluated. The materials investigated were Hi-Nicalon Type-S fiber reinforced chemically vapor infiltrated SiC matrix composites with varied interphases: monolayered pyrolytic carbon (PyC) or multilayered PyC/SiC. The neutron fluence was 7.7 1025 n/m2 (E>0.1 MeV), and the irradiation temperature was 800 C. Interfacial shear properties were evaluated by the fiber push-out test method. A modified shear-lag model was applied to analyze the interfacial shear parameters. Test results indicate that the interfacial debond shear strength and the interfacial friction stress for the multilayer composites were significantlymore »« less
https://doi.org/10.1016/j.jnucmat.2007.03.096

Similar Records