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

Conference · Fri Jul 01 04:00:00 EDT 2016

OSTI ID:22764074

Khalifa, H. E.; Sheeder, J. D.; Jacobsen, G. M.; Deck, C. P. ^[1]

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1. General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States)

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)

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22764074
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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