Corrosion behavior of Fe–Cr–Si alloys in simulated PWR primary water environment

Journal Article · 27 July 2019 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2019.07.035 · OSTI ID:1801218

Qiang, Rui ^[1]; Leong, Amanda ^[2]; Zhang, Jinsuo ^[2]; Short, Michael P. ^[3]

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1. Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States); Nuclear Power Inst. of China, Chengdu (China)
2. Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States)
3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

Fe–Cr–Si alloys are potential candidates as accident tolerant fuel (ATF) cladding, which could offer similar benefits as Fe–Cr–Al alloys. The corrosion and oxidation behaviors of three Fe–Cr–2Si alloys with various chromium content (12 wt. %, 16 wt. %, 20 wt. %) in simulated primary water chemistry of a pressurized water reactor (PWR) were investigated. Post-test characterization included weight change, scanning electron microscopy (SEM), and X-ray Photoelectron Spectroscopy (XPS). The results showed that Fe12Cr2Si had the worst corrosion/oxidation resistance among the three alloys, while Fe16Cr2Si and Fe20Cr2Si showed excellent oxidation resistance due to their thin, continuous, dense oxide layers grown in simulated PWR conditions. These results bring insight into the corrosion behavior of Fe–Cr–Si alloys with varying chromium content exposed to the primary water environment during normal operating conditions found in PWRs.

• Research Organization: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP); USDOE
• Grant/Contract Number: NE0008413
• OSTI ID: 1801218
• Alternate ID(s): OSTI ID: 1557903
• Journal Information: Journal of Nuclear Materials, Vol. 526; ISSN 0022-3115
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English