skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding

Abstract

Silicon carbide (SiC) and silicon carbide fiber reinforced, silicon carbide matrix (SiC-SiC) composites are candidate materials for nuclear fuel cladding in accident tolerant light water reactors and advanced high temperature reactors due to their chemical stability and retention of strength at elevated temperature and neutron flux. A reliable means to join silicon carbide components is imperative to the successful implementation of SiC-based structural nuclear materials as fuel cladding as well as more complex core internal structures. A comprehensive approach has been taken to address several of the significant challenges associated with SiC joining and fabrication of complex SiC structures. This work focuses on low activation joining materials that are expected to behave well under a variety of different reactor operating conditions. Pre- and post-irradiation mechanical testing and microstructural evaluation will be presented for specimens subjected to fast flux irradiation to 4.5 dpa at 730 C. degrees, as well as 8.7 dpa at 270 C. degrees. Joints did not exhibit any strength degradation under either irradiation condition. Additionally, the performance of joined cylindrical SiC-SiC composite specimens was evaluated following irradiation in pressurized water reactor (PWR) coolant chemistry to 0.5 dpa. Lastly, out-of-pile characterization of permeability has been conducted on joined cylindricalmore » SiC-SiC specimens to assess performance of this joint material under additional conditions relevant to reactor operation. Details of the experimental set-up and relationships between microstructure and performance will be discussed. (authors)« less

Authors:
; ; ;  [1]
  1. General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States)
Publication Date:
Research Org.:
American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22764074
Resource Type:
Conference
Resource Relation:
Conference: TOP FUEL 2016: LWR fuels with enhanced safety and performance, Boise, ID (United States), 11-15 Sep 2016; Other Information: Country of input: France; 22 refs.; Related Information: In: TOP FUEL 2016 Proceedings| 1670 p.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 42 ENGINEERING; ACCIDENT-TOLERANT NUCLEAR FUELS; CLADDING; CYLINDRICAL CONFIGURATION; FIBERS; IRRADIATION; JOINING; MECHANICAL TESTS; MICROSTRUCTURE; NEUTRON FLUX; PWR TYPE REACTORS; REACTOR OPERATION; REINFORCED MATERIALS; SILICON CARBIDES; TEMPERATURE RANGE 0400-1000 K

Citation Formats

Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., and Deck, C. P. Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. United States: N. p., 2016. Web.
Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. United States.
Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., and Deck, C. P. 2016. "Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding". United States.
@article{osti_22764074,
title = {Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding},
author = {Khalifa, H. E. and Sheeder, J. D. and Jacobsen, G. M. and Deck, C. P.},
abstractNote = {Silicon carbide (SiC) and silicon carbide fiber reinforced, silicon carbide matrix (SiC-SiC) composites are candidate materials for nuclear fuel cladding in accident tolerant light water reactors and advanced high temperature reactors due to their chemical stability and retention of strength at elevated temperature and neutron flux. A reliable means to join silicon carbide components is imperative to the successful implementation of SiC-based structural nuclear materials as fuel cladding as well as more complex core internal structures. A comprehensive approach has been taken to address several of the significant challenges associated with SiC joining and fabrication of complex SiC structures. This work focuses on low activation joining materials that are expected to behave well under a variety of different reactor operating conditions. Pre- and post-irradiation mechanical testing and microstructural evaluation will be presented for specimens subjected to fast flux irradiation to 4.5 dpa at 730 C. degrees, as well as 8.7 dpa at 270 C. degrees. Joints did not exhibit any strength degradation under either irradiation condition. Additionally, the performance of joined cylindrical SiC-SiC composite specimens was evaluated following irradiation in pressurized water reactor (PWR) coolant chemistry to 0.5 dpa. Lastly, out-of-pile characterization of permeability has been conducted on joined cylindrical SiC-SiC specimens to assess performance of this joint material under additional conditions relevant to reactor operation. Details of the experimental set-up and relationships between microstructure and performance will be discussed. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/22764074}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {7}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: