Chloride-Induced Stress Corrosion Cracking Characteristics of the Used Nuclear Fuel Canister Material
- Nuclear Engineering Program, The Ohio State University, 201 W 19th Ave, Columbus, OH 43210 (United States)
The used nuclear fuel (UNF) dry storage systems are located in the coastal and lake/river-side regions, the service time of which is 60 years and more. One type of dry storage systems is composite of a thin-walled austenitic stainless steel (SS) welded canister and a concrete overpack. The air flows through the canister surface and brings away the decay heat. Meanwhile, the air brings the salt species into the canister and make them deposit on the surface. The salt deposit will be deliquescent when absorbing the moisture air, being corrosive to the surface. NRC and other programs claimed that chloride induced stress corrosion cracking (CISCC) would lead to the canister failure, being one of the major technical gaps for extended dry storage systems. CISCC is induced by the combined influence of the aggressive environment (chloride ions in our case) and tensile stresses (residual stresses in our case) on the susceptible materials (the austenitic SS in our case). Chrome (Cr), as one of the chemical compositions of SSs, plays an important role in the corrosion resistance. It can form a chrome-rich inner barrier oxide layer to prevent the SS from corrosion. However, chloride ions can easily break down the barrier and accelerate dissolution of the underlying metal, the phenomena of which is pitting corrosion. Pitting is the precursor to CISCC as which provides the combination of a local aggressive solution chemistry and a stress concentrating feature. Accordingly, CISCC invariably originates from the pits, and cracks that have nucleated on pit walls can grow around the pit and coalesce to form a complete through-crack. Significant tensile residual stresses, caused by the welding process, exist throughout the thickness of the canister wall. Enos and Bryan found that large residual stresses were in the full-scale mockup container simulating a canister, which supports the SCC propagation. It is therefore interesting to achieve a good knowledge about the effect of welding on the durability of SSs, especially in the corrosive environment. In order to understand the fundamental of the cracking behaviors, it's vital to elucidate the microstructure and microchemistry of cracking. This study focused on observing the CISCC characteristics of the UNF canister material exposed to the humid environment with salt deposit. Extensive micro-characteristics have been achieved by the techniques include focused ion beam/ scanning electron microscope (FIB/SEM), transmission electron microscopy (TEM), energy dispersive spectroscopy (EDS), and optical profiler. (authors)
- OSTI ID:
- 23042630
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 115; Conference: 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, NV (United States), 6-10 Nov 2016; Other Information: Country of input: France; 6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US); ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
AFTER-HEAT
AIR FLOW
AUSTENITIC STEELS
CHEMICAL COMPOSITION
CHLORINE IONS
CORROSION RESISTANCE
CRACKING
DRY STORAGE
ION BEAMS
MICROSTRUCTURE
NUCLEAR FUELS
OXIDES
PITTING CORROSION
RESIDUAL STRESSES
SALT DEPOSITS
SCANNING ELECTRON MICROSCOPY
SPECTROSCOPY
STRESS CORROSION
TRANSMISSION ELECTRON MICROSCOPY
WELDING