Diana A. Merezhko , Mikhail S. Merezhko , Michael P. Short
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引用次数: 0
Abstract
Advanced ferritic-martensitic (F/M) steels are often used in sodium-cooled fast nuclear reactors (SFRs), given their superior resistance to swelling, high-temperature embrittlement, and radiation creep. However, a potential vulnerability of F/M steels lies in their low corrosion resistance to prolonged storage in water-filled spent fuel pools. This poses a significant challenge, especially during fuel storage and reactor decommissioning, increasing the risk of radioactive contamination, safety hazards, and substantial financial costs. Here we show and explain significant corrosion susceptibility of EP-450 ferritic-martensitic steel (1Cr13Mo2NbBV) after irradiation in the BN-350 SFR up to 70 dpa and subsequent long-term (20 years at <50 °C) wet storage in the reactor's spent fuel pool. Corrosion morphologies ranged from oxide films to various forms of localized degradation, including very deep pitting, phase-selective attack, intragranular attack, and interphase corrosion. Deep pits mechanistically form via the preferential dissolution of phase boundaries and the tempered martensitic phase, leading to the eventual detachment of unaffected ferrite grains. The presence and preferential dissolution of the tempered martensitic phase, which is absent in ferritic or austenitic steels, is the dominant factor driving this severe localized corrosion damage in EP-450 steel.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.