Corrosion and Compatibility in Advanced Reactor Systems ENVIRONMENT CANDIDATE MATERIALS liquid...
-
Upload
dulcie-lloyd -
Category
Documents
-
view
219 -
download
0
Transcript of Corrosion and Compatibility in Advanced Reactor Systems ENVIRONMENT CANDIDATE MATERIALS liquid...
Corrosion and Compatibility in
Advanced Reactor Systems
ENVIRONMENT CANDIDATE MATERIALS
liquid metals Na iron based alloys Pb-Bi iron based
helium/graphite Ni based alloys
supercritical water Fe,Ni,Ti,Zr, based alloys stress corrosion cracking
molten salt
Hugh IsaacsBNL
liquid metal compatibility
solubility in liquid metal construction alloys interstitials O, C, N, H
solid surfaces
extraction insertion
products
mass transport gradients in liquid activity in solids reaction
Pb/Pb-Bi
corrosion inhibition of ferritic steels by 50-500 ppm Zr, Ti forms nitrides or nitrides+carbides on steel surfaces
6000 h CrMoV steel
300–500 ppm Mg
300 h 2CrSiMoV steel
300–500 ppm Mg + 10-40 ppm Ti
600 C
Wright 2008Quadakkers 1988
stronglyreducing
highly oxidizing
highly carburizing
bestregion
carburizing under oxide
“thermodynamic” representation of alloy behavior
He
Supercritical water
Ferritic–martensitic Austenitic Ni-based
weight gain largest weight gain < ferritic-m little weight gainthan ferritic–martensitic complex parametrics except below the pseudo-criticalCr reduces rate good grain boundary eng. precipitate hardened pitlowest rates at 300 ppb Oimplant Y - major improvement
Zirconium Titanium
std alloys corrode optimized comps ~ austeniticoptimized comp > austenitics
alloy systems under study
Was et al. (2007)
Stress Corrosion Cracking
Supercritical water
austenitic IGSCC > ferritic-martensitic
acidic additions increase cracking
higher Cr increases susceptibility to HCl
increased pressure increases SCC
ferritic -m in pure systems resistant to 600 C