Effects of hydrogen peroxide on 304 stainless steel in high temperature water (original) (raw)
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Oxidation of Metals
The effect of p(H 2 O) and p(H 2) on the oxidation of 304L stainless steel at 600°C has been investigated in the present study. The samples were analysed by means of X-ray diffraction, Auger spectroscopy, and scanning electron microscopy equipped with energy dispersive spectroscopy. The results showed that at fixed p(H 2), the corrosion rate increased considerably with increasing p(H 2 O). At fixed p(H 2 O), the corrosion rate decreased slightly with increasing p(H 2). Duplex oxide scales formed during the exposure in all environments. The outer and inner layer consisted of Fe 3 O 4 and (Fe, Cr) 3 O 4 , respectively. The latter was mainly in the form of internal oxidation. The Cr-rich oxide formation was observed at the initial oxidation process before oxide breakdown. The Auger analysis also suggested the presence of Cr-rich oxide layer just after the breakaway oxidation. The results indicated that the rate-determining step in the corrosion attack is surface controlled or diffusion controlled through an oxide layer with fixed thickness over time.
Corrosion behavior of 304 stainless steel in high temperature, hydrogenated water
Corrosion Science, 2002
The corrosion behavior of an austenitic stainless steel (UNS S30400) has been characterized in a 10,000 h test conducted in hydrogenated, ammoniated water at 260°C. The corrosion kinetics were observed to be parabolic, the parabolic rate constant being determined by chemical descaling to be 1.16 mg dm À2 h À1=2 . X-ray photoelectron spectroscopy, in combination with argon ion milling and target factor analysis, was applied to provide an independent estimate of the rate constant that agreed with the gravimetric result. Based on the distribution of the three oxidized alloying constituents (Fe, Cr, Ni) with respect to depth and elemental state, it was found that: (a) corrosion occurs in a non-selective manner, and (b) the corrosion film consists of two spinel oxide layers--a ferrite-based outer layer (Ni 0:2 Fe 0:8 )(Fe 0:95 Cr 0:05 ) 2 O 4 on top of a chromite-based inner layer (Ni 0:2 Fe 0:8 )(Cr 0:7 Fe 0:3 ) 2 O 4 . These compositions agree closely with the solvi phases created by immiscibility in the Fe 3 O 4 -FeCr 2 O 4 binary, implying that immiscibility plays an important role in the phase separation process. Ó
Influence of Irradiation on the Oxide Film Formed on 316 L Stainless Steel in PWR Primary Water
Oxidation of Metals, 2013
Oxidation of stainless steel in PWR primary water at 325°C was studied by investigating the influence of defects created at the alloy subsurface by proton irradiation before corrosion exposure. Corrosion experiments were conducted by sequentially exposing samples, with H 2 18 O used for the second exposure. The oxide layer, formed in these conditions was studied by SEM and TEM and could be divided in two parts: an external discontinuous layer composed of crystallites rich in iron and an internal continuous layer richer in chromium. Tracer experiments revealed that the growth of this protective scale was due to oxygen diffusion in the grain boundary of the oxide layer. Defects created by irradiation have an effect on the two oxide layers. They are a preferential nucleation site for the external layer and so increase the density of the crystallites. They also induce a slower diffusion of oxygen in the internal layer.
Corrosion Science, 2014
Samples of 316L were exposed at 325°C to PWR primary water labelled with deuterium and oxygen 18. The SIMS and GD-OES analysis has revealed the presence of deuterium in the internal oxide layer and in the underlying alloy. Two-stage corrosion experiments have shown that the oxygen and hydrogen transport in the oxide layer is not coupled and that the short-circuit diffusion coefficient of 18 O in the oxide scale: D sc = (9 ± 1)Á10 À17 cm 2 s À1. These results are used to propose a mechanism describing the anionic growth of the protective oxide layer and the concomitant adsorption of hydrogen in the alloy.
The influence of hydrogen peroxide and hydrogen on the corrosion of simulated spent nuclear fuel
Faraday Discussions, 2015
The synergistic influence between H2O2 and H2 on the corrosion of SIMFUEL (simulated spent nuclear fuel) has been studied in solutions with and without added HCO3−/CO32−. The response of the surface to increasing concentrations of added H2O2 was monitored by measuring the corrosion potential in either Ar or Ar/H2-purged solutions. Using X-ray photoelectron spectroscopy it was shown that the extent of surface oxidation (UV + UVI content) was directly related to the corrosion potential. Variations in corrosion potential with time, redox conditions, HCO3−/CO32− concentration, and convective conditions showed that surface oxidation induced by H2O2 could be reversed by reaction with H2, the latter reaction occurring dominantly on the noble metal particles in the SIMFUEL. For sufficiently large H2O2 concentrations, the influence of H2 was overwhelmed and irreversible oxidation of the surface to UVI occurred. Subsequently, corrosion was controlled by the chemical dissolution rate of this U...
Metallurgical Transactions A, 1983
Corrosion of SAE 310 stainless steel in H2-1120-112S bas mixtures was studied at a constant temperature of 1150 K. Reactive gas mixtures were chosen to yield a constant oxygen potential of approximately 6 x 10-13 Nm-2 and sulfur potentials ranging from 0.19 x 10-2 Nm 2 to 33 x 10-2 Nm-2. The kinetics of corrosion were determined using a thermobalance, and the scales were analyzed using metallography, scanning electron microscopy, and energy dispersive x-ray analysis. Two corrosion regimes, which were dependent on sulfur pol ential, were identified. At high sulfur potentials (I' G ^ 2.7), 10-.'Nm-') the corrosion rates were high, the kinetics obeyed a linear rate equation, and the scales consisted mainly of sulfide 1). BHOGESWARA RAO was a Research Scientist, Materials and Molecular Research Division, Lawrence Berkeley laboratory, Berkele y , Calif. 04120. His present address is Hewlett-Packard, 10900 Wolfe Road, Cupert ino, C.il it.
Effects of Zn(II) on hydrogen peroxide-induced corrosion of stainless steel
Journal of Physics: Conference Series, 2019
Zinc injection has been widely applied in nuclear industry for corrosion mitigation of nuclear materials. The corrosion resistance mechanism of zinc in the presence of the radiolytic oxidizing species is complex and has not been completely understood. Without such information it is not possible to improve the protocol. In the present study, zinc effects on corrosion of 304 SS exposed to H2O2 at 200-1000 ppb for 7 and 70 hrs were investigated at room temperature using a custom-made flow setup. XRF and SEM-EDX were used to examine the chemical composition and surface morphology of the specimens. The results indicated that pitting was the dominant form of corrosion found under the experimental conditions. Zinc ions tend to help mitigate corrosion of the material via playing a significant role in oxide formation on the steel surface.
Revista de Chimie
Selecting proper candidate materials is one key issue for the development of the supercritical water-cooled nuclear reactor (SCWR). Designing or choosing the most fitting materials means better sustainability, economics and safety. As the supercritical water is a very aggressive corrosive media, corrosion becomes one challenging problem for the materials used in the SCWR. This paper involves the corrosion testing of two stainless steels (304L and 310S) and microstructure evaluation of samples after being exposed to supercritical water. The test parameters were set at the temperature of 550oC and the pressure of 25 MPa for up to 63 days. The samples were investigated using gravimetric corrosion test, optical microscopy, scanning electron microscopy coupled with energy dispersive X-ray spectroscopy. Results showed a lower corrosion performance, in terms of weight change and surface oxide formation, for 304L due to its low chromium content. 310S has excellent corrosion resistance becau...
Corrosion Experiment on Non Standard Austenitic Steel A1, in Reactor Coolant Water
Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir, 2013
CORROSION EXPERIMENT ON NON STANDARD AUSTENITIC STEEL A1, IN REACTOR COOLANT WATER. Experimental corrosion studies on non standar austenitic SS, A1, have been carried out. The samples were immersed in reactor coolant water medium with pH variation of 5.95, 6.0, 6.l5, and 6.31. The experiments were carried out using a type of M-273 EG&G potentiostate /galvanometer test instrument. The post-corrosion samples' microstructure were analyzed with the aid of EDS (energy dispersive spectroscopy) equipped SEM instrument to detect the presence of any viable corrosion products. For further verification x-ray diffraction method was also used to detect any possible emerging corrosion products type on the samples' surfaces. Experimental results confirm that non standar austenitic SS immersed in reactor coolant water corrosion medium with a variation of concentration experience very little or almost no corrosion, and that according to the so-called Fontana's criteria these test-materials turn out to have an excellent resistance toward reactor coolant water corrosion medium. This is also evidenced by the very low corrosion rate value measured in this study. EDS study and X-ray diffraction results indicate that the possible ensuing corrosion byproducts are chrome oxides and iron oxides.