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

Koyanagi, T.; Katoh, Y.; Kiggans, J. O.; Hinoki, T.; Khalifa, H. E.; Deck, C. P.; Back, C. A.

doi:10.1016/j.jnucmat.2017.03.017

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

Journal Article · Fri Mar 10 00:00:00 EST 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.03.017· OSTI ID:1347314

Koyanagi, T. ^[1]; Katoh, Y. ^[1]; Kiggans, J. O. ^[1]; Hinoki, T. ^[2]; Khalifa, H. E. ^[3]; Deck, C. P. ^[3]; Back, C. A. ^[3]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Kyoto Univ. (Japan)
General Atomics, San Diego, CA (United States)

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.

View Accepted Manuscript (DOE)

View Accepted Manuscript (Publisher)

Cite

Export

Save

Research Organization:: 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 Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725; RC0304000

OSTI ID:: 1347314

Alternate ID(s):: OSTI ID: 1396901

Journal Information:: Journal of Nuclear Materials, Vol. 488, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 17 works

Citation information provided by
Web of Science

References (17)

Current status and recent research achievements in SiC/SiC composites Katoh, Y.; Snead, L. L.; Henager, C. H. Journal of Nuclear Materials, Vol. 455, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.003	journal	December 2014
Accident tolerant fuels for LWRs: A perspective Zinkle, S. J.; Terrani, K. A.; Gehin, J. C. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.005	journal	May 2014
Characteristics of Composite Silicon Carbide Fuel Cladding after Irradiation under Simulated PWR Conditions Stempien, John D.; Carpenter, David M.; Kohse, Gordon Nuclear Technology, Vol. 183, Issue 1 https://doi.org/10.13182/NT12-86	journal	July 2013
Radiation-tolerant joining technologies for silicon carbide ceramics and composites Katoh, Yutai; Snead, Lance L.; Cheng, Ting Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.002	journal	May 2014
Handbook of SiC properties for fuel performance modeling Snead, Lance L.; Nozawa, Takashi; Katoh, Yutai Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.016	journal	September 2007
Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature 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 https://doi.org/10.1016/j.nimb.2016.01.005	journal	March 2016
Development of a shear strength test method for NITE–SiC joining material Jung, Hun-Chea; Hinoki, Tatsuya; Katoh, Yutai Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.082	journal	October 2011
Bonding of ceramics: An analysis of the torsion hourglass specimen Goglio, L.; Ferraris, M. International Journal of Adhesion and Adhesives, Vol. 70 https://doi.org/10.1016/j.ijadhadh.2016.05.006	journal	October 2016
Effect of Ti and Si Interlayer Materials on the Joining of SiC Ceramics Jung, Yang-Il; Park, Jung-Hwan; Kim, Hyun-Gil Nuclear Engineering and Technology, Vol. 48, Issue 4 https://doi.org/10.1016/j.net.2016.03.001	journal	August 2016
Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form Terrani, K. A.; Kiggans, J. O.; Silva, C. M. Journal of Nuclear Materials, Vol. 457 https://doi.org/10.1016/j.jnucmat.2014.10.034	journal	February 2015
Effect of neutron irradiation on select MAX phases Tallman, Darin J.; Hoffman, Elizabeth N.; Caspi, El’ad N. Acta Materialia, Vol. 85 https://doi.org/10.1016/j.actamat.2014.10.068	journal	February 2015
Modeling and testing miniature torsion specimens for SiC joining development studies for fusion Henager, C. H.; Nguyen, B. N.; Kurtz, R. J. Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.07.044	journal	November 2015
The influence of sintering additives on the irradiation resistance of NITE SiC Koyanagi, Takaaki; Kondo, Sosuke; Hinoki, Tatsuya Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.181	journal	October 2011
Fabrication and characterization of joined silicon carbide cylindrical components for nuclear applications Khalifa, H. E.; Deck, C. P.; Gutierrez, O. Journal of Nuclear Materials, Vol. 457 https://doi.org/10.1016/j.jnucmat.2014.11.071	journal	February 2015
Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials Ang, Caen; Silva, Chinthaka; Shih, Chunghao Scripta Materialia, Vol. 114 https://doi.org/10.1016/j.scriptamat.2015.11.008	journal	March 2016
Stability of SiC-matrix microencapsulated fuel constituents at relevant LWR conditions Snead, L. L.; Terrani, K. A.; Katoh, Y. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.056	journal	May 2014
Dimensional isotropy of 6H and 3C SiC under neutron irradiation Snead, Lance L.; Katoh, Yutai; Koyanagi, Takaaki Journal of Nuclear Materials, Vol. 471 https://doi.org/10.1016/j.jnucmat.2016.01.010	journal	April 2016

Cited By (3)

Zr–Cu alloy filler metal for brazing SiC ceramic Zhou, Bofang; Feng, Keqin RSC Advances, Vol. 8, Issue 46 https://doi.org/10.1039/c8ra05480k	journal	January 2018
Molecular dynamics simulations of silicon carbide nanowires under single-ion irradiation He, Wanzhen; Chen, Changqing; Xu, Zhiping Journal of Applied Physics, Vol. 126, Issue 12 https://doi.org/10.1063/1.5121873	journal	September 2019
Study on the wetting interface of Zr–Cu alloys on the SiC ceramic surface Zhou, Bofang; Wang, Jinfeng; Feng, Keqin RSC Advances, Vol. 10, Issue 6 https://doi.org/10.1039/c9ra10723a	journal	January 2020

Similar Records

Radiation Tolerance of Silicon Carbide Joints at LWR Relevant Temperature

Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1347314

Koyanagi, Takaaki; Katoh, Yutai; Kiggans, James O.; +2 more

Hydrothermal corrosion of silicon carbide joints without radiation

Journal Article · Wed Sep 28 00:00:00 EDT 2016 · Journal of Nuclear Materials · OSTI ID:1347314

Koyanagi, Takaaki; Katoh, Yutai; Terrani, Kurt A.; +3 more

Progress in development of SiC-based joints resistant to neutron irradiation

Journal Article · Fri Nov 15 00:00:00 EST 2019 · Journal of the European Ceramic Society · OSTI ID:1347314

Koyanagi, Takaaki; Kato, Yutai; Hinoki, Tatsuya; +3 more

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

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

Citation Formats

References (17)

Cited By (3)

Similar Records

Related Subjects