Mechanical properties of advanced SiC/SiC composites after neutron irradiation
- 1. Kyoto Univ., Graduate School of Energy Science, Uji, Kyoto (Japan)
- 2. Metals and Ceramics Division, Oak Ridge National Laboratroy, Oak Ridge, TN (United States)
- 3. Kyoto Univ., Inst. of Advanced Energy, Uji, Kyoto (Japan)
Description
The neutron irradiation effect on tensile properties in advanced 2D-SiC/SiC composites were evaluated. The composites used were composed of a SiC matrix obtained by FCVI process and either Tyranno-SA 3rd grade (TySA) or Hi-Nicalon Type-S fiber with singly-layered PyC. Neutron irradiation fluence and temperature were 3.1x1025n/m2 (E>0.1 MeV) at 740degC and 1.2x1026n/m2 at 750degC, respectively. Tensile properties were evaluated by unloading /reloading cyclic tensile test, and hysteresis loop analysis was applied in order to predict interfacial properties. Both composites exhibited excellent irradiation resistance in ultimate and proportional limit tensile stresses. From the hysteresis loop analysis, the level of interfacial sliding stress was decreased significantly after irradiation to 1.2x1026n/m2 at 750degC. (author)
Additional details
Publishing Information
- Imprint Title
- Summary report of Japan-US joint project. JUPITER-II. FuY 2001 - 2006
- Imprint Pagination
- 354 p.
- Journal Page Range
- p. 273-277
- Report number
- NIFS-PROC--71
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 40104409
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COMPOSITE MATERIALS; DAMAGE; FIBERS; HYSTERESIS; IRRADIATION; MATRIX MATERIALS; MICROSTRUCTURE; NEUTRONS; PYROLYTIC CARBON; SILICON CARBIDES; STRAINS; STRESS ANALYSIS; STRESSES; TENSILE PROPERTIES; THERMONUCLEAR REACTOR MATERIALS
- Descriptors DEC
- BARYONS; CARBIDES; CARBON; CARBON COMPOUNDS; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; HADRONS; MATERIALS; MECHANICAL PROPERTIES; NONMETALS; NUCLEONS; SILICON COMPOUNDS
Optional Information
- Notes
- 20 refs., 5 figs., 1 tab.