DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature

Abstract

We fabricated and irradiated monolithic silicon carbide (SiC) to SiC plate joints with neutrons at 270–310 °C to 8.7 dpa for SiC. The joining methods included solid state diffusion bonding using titanium and molybdenum interlayers, SiC nanopowder sintering, reaction sintering with a Ti-Si-C system, and hybrid processing of polymer pyrolysis and chemical vapor infiltration (CVI). All the irradiated joints exhibited apparent shear strength of more than 84 MPa on average. Significant irradiation-induced cracking was found in the bonding layers of the Ti and Mo diffusion bonds and Ti-Si-C reaction sintered bond. Furthermore, the SiC-based bonding layers of the SiC nanopowder sintered and hybrid polymer pyrolysis and CVI joints all showed stable microstructure following the irradiation.

Authors:
 [1];  [1];  [1];  [2];  [3];  [3];  [3]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Kyoto Univ. (Japan)
  3. General Atomics, San Diego, CA (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Temperature Materials Lab. (HTML)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1347314
Alternate Identifier(s):
OSTI ID: 1396901
Grant/Contract Number:  
AC05-00OR22725; RC0304000
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 488; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Koyanagi, T., Katoh, Y., Kiggans, J. O., Hinoki, T., Khalifa, H. E., Deck, C. P., and Back, C. A. Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature. United States: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.03.017.
Koyanagi, T., Katoh, Y., Kiggans, J. O., Hinoki, T., Khalifa, H. E., Deck, C. P., & Back, C. A. Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature. United States. https://doi.org/10.1016/j.jnucmat.2017.03.017
Koyanagi, T., Katoh, Y., Kiggans, J. O., Hinoki, T., Khalifa, H. E., Deck, C. P., and Back, C. A. Fri . "Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature". United States. https://doi.org/10.1016/j.jnucmat.2017.03.017. https://www.osti.gov/servlets/purl/1347314.
@article{osti_1347314,
title = {Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature},
author = {Koyanagi, T. and Katoh, Y. and Kiggans, J. O. and Hinoki, T. and Khalifa, H. E. and Deck, C. P. and Back, C. A.},
abstractNote = {We fabricated and irradiated monolithic silicon carbide (SiC) to SiC plate joints with neutrons at 270–310 °C to 8.7 dpa for SiC. The joining methods included solid state diffusion bonding using titanium and molybdenum interlayers, SiC nanopowder sintering, reaction sintering with a Ti-Si-C system, and hybrid processing of polymer pyrolysis and chemical vapor infiltration (CVI). All the irradiated joints exhibited apparent shear strength of more than 84 MPa on average. Significant irradiation-induced cracking was found in the bonding layers of the Ti and Mo diffusion bonds and Ti-Si-C reaction sintered bond. Furthermore, the SiC-based bonding layers of the SiC nanopowder sintered and hybrid polymer pyrolysis and CVI joints all showed stable microstructure following the irradiation.},
doi = {10.1016/j.jnucmat.2017.03.017},
journal = {Journal of Nuclear Materials},
number = C,
volume = 488,
place = {United States},
year = {Fri Mar 10 00:00:00 EST 2017},
month = {Fri Mar 10 00:00:00 EST 2017}
}

Journal Article:

Citation Metrics:
Cited by: 17 works
Citation information provided by
Web of Science

Save / Share:

Works referenced in this record:

Current status and recent research achievements in SiC/SiC composites
journal, December 2014


Accident tolerant fuels for LWRs: A perspective
journal, May 2014


Characteristics of Composite Silicon Carbide Fuel Cladding after Irradiation under Simulated PWR Conditions
journal, July 2013

  • Stempien, John D.; Carpenter, David M.; Kohse, Gordon
  • Nuclear Technology, Vol. 183, Issue 1
  • DOI: 10.13182/NT12-86

Radiation-tolerant joining technologies for silicon carbide ceramics and composites
journal, May 2014


Handbook of SiC properties for fuel performance modeling
journal, September 2007


Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature
journal, March 2016

  • Campbell, Anne A.; Porter, Wallace D.; Katoh, Yutai
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 370
  • DOI: 10.1016/j.nimb.2016.01.005

Development of a shear strength test method for NITE–SiC joining material
journal, October 2011


Bonding of ceramics: An analysis of the torsion hourglass specimen
journal, October 2016


Effect of Ti and Si Interlayer Materials on the Joining of SiC Ceramics
journal, August 2016

  • Jung, Yang-Il; Park, Jung-Hwan; Kim, Hyun-Gil
  • Nuclear Engineering and Technology, Vol. 48, Issue 4
  • DOI: 10.1016/j.net.2016.03.001

Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form
journal, February 2015


Effect of neutron irradiation on select MAX phases
journal, February 2015


Modeling and testing miniature torsion specimens for SiC joining development studies for fusion
journal, November 2015


The influence of sintering additives on the irradiation resistance of NITE SiC
journal, October 2011


Fabrication and characterization of joined silicon carbide cylindrical components for nuclear applications
journal, February 2015


Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials
journal, March 2016


Stability of SiC-matrix microencapsulated fuel constituents at relevant LWR conditions
journal, May 2014


Dimensional isotropy of 6H and 3C SiC under neutron irradiation
journal, April 2016


Works referencing / citing this record:

Zr–Cu alloy filler metal for brazing SiC ceramic
journal, January 2018


Molecular dynamics simulations of silicon carbide nanowires under single-ion irradiation
journal, September 2019

  • He, Wanzhen; Chen, Changqing; Xu, Zhiping
  • Journal of Applied Physics, Vol. 126, Issue 12
  • DOI: 10.1063/1.5121873

Study on the wetting interface of Zr–Cu alloys on the SiC ceramic surface
journal, January 2020

  • Zhou, Bofang; Wang, Jinfeng; Feng, Keqin
  • RSC Advances, Vol. 10, Issue 6
  • DOI: 10.1039/c9ra10723a