Publication Type
Journal
Journal Name
Journal of Nuclear Materials
Publication Date
Page Number
152190
Volume
536
Issue
1
Abstract
Chemical vapor deposited (CVD) SiC and nuclear-grade SiC/SiC composite materials were exposed to light water reactor (LWR) conditions at the MIT Nuclear Reactor (MITR). Three sets of samples were exposed within flowing PWR-chemistry-coolant under either 1) neutron and ionizing irradiation with resulting radiolysis products, 2) radiolysis products without neutron flux, 3) loop coolant. Post-irradiation examination (PIE) demonstrated an increase in corrosion from radiolysis products (particularly H2O2), and potentially a further increase from radiation damage. For CVD SiC, regardless of exposure location, the in-situ observed corrosion rate was less than 1 μm per year, potentially within acceptable limits for LWR application.
