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Electrochemical experiments with multi-phase alloy and alloy/ceramic composite materials representing waste forms being developed for metallic high-level radioactive waste streams generated during the pyroprocessing of spent nuclear fuel.
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An experimental setup was used to study the effect of the environmental parameters on the corrosion process. In particular, water conductivity and sensitivity to temperature were investigated.
A large power transmitter completed a multiyear corrosion study to verify the corrosion rate models for zinc and steel. As a result of that study, a long term field corrosion monitoring program, at 125 sites, was initiated.
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Nuclear wastes are stored in large, underground carbon steel storage tanks. Carbon steels can be susceptible to localized corrosion (e.g., pitting) and stress corrosion cracking (SCC). This paper presents work done to evaluate changes in SCC susceptibility over time.
Numerical modeling software is used to fit the real field AC interference data to verify the rationality of related boundary settings. Then possible AC mitigation solutions are evaluated and optimized based on the verified software boundary settings.
This paper outlines the approach taken to select a promising salt (KCl - 44.5 wt% NaCl), and containment materials (UNS S31600 and UNS N08330 with G10180 as the control/baseline).
The corrosion of stainless steel AISI 309S, one of the recommended materials, was investigated in a representative salt brine by a special designed high-pressure and high-temperature electrochemical reactor.