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Title: PIE of nuclear grade SiC/SiC flexural coupons irradiated to 10 dpa at LWR temperature

Abstract

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, dynamic Young’s modulus, swelling, and microstructures. There was no notable mechanical properties degradation of the irradiated HNS and SA3 SiC/SiC composites except for reduction of the Young’s moduli by up to 18%. The microstructural stability of these composites supported the absence of degradation. In addition, no progressive swelling from 2.0 to 11.8 dpa was confirmed for these composites. On the other hand, the SCS composite showed significant mechanical degradation associated with cracking within the fiber. This study determined that SiC/SiC composites with HNS or SA3 SiC/SiC fibers, a PyC interphase, and a CVI SiC matrix retain their properties beyondmore » the lifetime dose for LWR fuel cladding at the relevant temperature.« less

Authors:
 [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1360077
Report Number(s):
ORNL/TM-2017/136
AF5810000; NEAF278; ORNL/SR-2017/136
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; Light Water Reactors

Citation Formats

Koyanagi, Takaaki, and Katoh, Yutai. PIE of nuclear grade SiC/SiC flexural coupons irradiated to 10 dpa at LWR temperature. United States: N. p., 2017. Web. doi:10.2172/1360077.
Koyanagi, Takaaki, & Katoh, Yutai. PIE of nuclear grade SiC/SiC flexural coupons irradiated to 10 dpa at LWR temperature. United States. doi:10.2172/1360077.
Koyanagi, Takaaki, and Katoh, Yutai. Wed . "PIE of nuclear grade SiC/SiC flexural coupons irradiated to 10 dpa at LWR temperature". United States. doi:10.2172/1360077. https://www.osti.gov/servlets/purl/1360077.
@article{osti_1360077,
title = {PIE of nuclear grade SiC/SiC flexural coupons irradiated to 10 dpa at LWR temperature},
author = {Koyanagi, Takaaki and Katoh, Yutai},
abstractNote = {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-UltraTM (SCS) SiC fibers. The irradiation resistance of these composites was investigated based on flexural behavior, dynamic Young’s modulus, swelling, and microstructures. There was no notable mechanical properties degradation of the irradiated HNS and SA3 SiC/SiC composites except for reduction of the Young’s moduli by up to 18%. The microstructural stability of these composites supported the absence of degradation. In addition, no progressive swelling from 2.0 to 11.8 dpa was confirmed for these composites. On the other hand, the SCS composite showed significant mechanical degradation associated with cracking within the fiber. This study determined that SiC/SiC composites with HNS or SA3 SiC/SiC fibers, a PyC interphase, and a CVI SiC matrix retain their properties beyond the lifetime dose for LWR fuel cladding at the relevant temperature.},
doi = {10.2172/1360077},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {3}
}

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