Evaluation of neutron irradiated silicon carbide and silicon carbide composites
- 1. Lockheed Martin Corporation, Schenectady, NY 12301 (United States)
- 2. Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37830 (United States)
- 3. Current Address, Kyoto University, Uji Campus (Japan)
Description
The effects of fast neutron irradiation on SiC and SiC composites have been studied. The materials used were chemical vapor deposition (CVD) SiC and SiC/SiC composites reinforced with either Hi-NicalonTM Type-S, Hi-NicalonTM or SylramicTM fibers fabricated by chemical vapor infiltration. A statistically significant population of flexural samples were irradiated up to 4.6 x 1025 n/m2 (E > 0.1 MeV) at 300, 500, and 800 deg. C in the High Flux Isotope Reactor at Oak Ridge National Laboratory. Dimensions and weights of the flexural bars were measured before and after the neutron irradiation. Mechanical properties were evaluated by four point flexural testing. Volume increase was seen for all bend bars following neutron irradiation. The magnitude of swelling depended on irradiation temperature and material, while it was nearly independent of irradiation fluence over the fluence range studied. Flexural strength of CVD SiC increased following irradiation depending on irradiation temperature. Over the temperature range studied, no significant degradation in mechanical properties was seen for composites fabricated with Hi-NicalonTM Type-S, while composites reinforced with Hi-NicalonTM or Sylramic fibers showed significant degradation. The effects of irradiation on the Weibull failure statistics are also presented suggesting a reduction in the Weibull modulus upon irradiation. The cause of this potential reduction is not known
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2007.05.007Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2007.05.007;
- PII
- S0022-3115(07)00742-8;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 371
- Journal Issue
- 1-3
- Journal Page Range
- p. 76-89
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 1. symposium on nuclear fuels and structural materials for next generation nuclear reactors
- Dates
- 4-8 Jun 2006
- Place
- Reno, NV (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39048794
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHEMICAL VAPOR DEPOSITION; FAST NEUTRONS; FIBERS; FLEXURAL STRENGTH; HFIR REACTOR; IRRADIATION; MEV RANGE; NEUTRON BEAMS; PHYSICAL RADIATION EFFECTS; SILICON CARBIDES; SWELLING; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; TESTING
- Descriptors DEC
- BARYONS; BEAMS; CARBIDES; CARBON COMPOUNDS; CHEMICAL COATING; DEFORMATION; DEPOSITION; ELEMENTARY PARTICLES; ENERGY RANGE; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MECHANICAL PROPERTIES; NEUTRONS; NUCLEON BEAMS; NUCLEONS; PARTICLE BEAMS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SILICON COMPOUNDS; SURFACE COATING; TANK TYPE REACTORS; TEMPERATURE RANGE; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.