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Title: STATUS OF HIGH FLUX ISOTOPE REACTOR IRRADIATION OF SILICON CARBIDE/SILICON CARBIDE JOINTS

Technical Report ·
DOI:https://doi.org/10.2172/1164258· OSTI ID:1164258

Development of silicon carbide (SiC) joints that retain adequate structural and functional properties in the anticipated service conditions is a critical milestone toward establishment of advanced SiC composite technology for the accident-tolerant light water reactor (LWR) fuels and core structures. Neutron irradiation is among the most critical factors that define the harsh service condition of LWR fuel during the normal operation. The overarching goal of the present joining and irradiation studies is to establish technologies for joining SiC-based materials for use as the LWR fuel cladding. The purpose of this work is to fabricate SiC joint specimens, characterize those joints in an unirradiated condition, and prepare rabbit capsules for neutron irradiation study on the fabricated specimens in the High Flux Isotope Reactor (HFIR). Torsional shear test specimens of chemically vapor-deposited SiC were prepared by seven different joining methods either at Oak Ridge National Laboratory or by industrial partners. The joint test specimens were characterized for shear strength and microstructures in an unirradiated condition. Rabbit irradiation capsules were designed and fabricated for neutron irradiation of these joint specimens at an LWR-relevant temperature. These rabbit capsules, already started irradiation in HFIR, are scheduled to complete irradiation to an LWR-relevant dose level in early 2015.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
U.S. Department of Energy, Office of Nuclear Energy, for the Light Water Reactor Sustainability (LWRS) program; Irradiation in the High Flux Isotope Reactor is sponsored by the Scientific User Facilities Division, Office of Basic Energy Sciences
Contributing Organization:
High Flux Isotope Reactor (HFIR) User Facility
DOE Contract Number:
DE-AC05-00OR22725
OSTI ID:
1164258
Report Number(s):
ORNL/TM-2014/513; R&D Project: 619156301
Country of Publication:
United States
Language:
English