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- W3022632009 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 H 2 O 2 ), 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. • CVD SiC lost less than 1 μm in thickness/year in BWR-HWC conditions with 4wppm H 2 . • Radiation damage and radiolysis exacerbated corrosion significantly. • Localized attack was observed only on samples exposed to damage and radiolysis." @default.
- W3022632009 created "2020-05-13" @default.
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- W3022632009 date "2020-08-01" @default.
- W3022632009 modified "2023-10-16" @default.
- W3022632009 title "The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC" @default.
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- W3022632009 doi "https://doi.org/10.1016/j.jnucmat.2020.152190" @default.
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