Characterization of corrosion phenomena and kinetics on T91 ferritic/martensitic steel exposed at 450 and 550 °C to flowing Pb-Bi eutectic with 10−7 mass% dissolved oxygen

Tsisar, Valentyn; Schroer, Carsten; Wedemeyer, Olaf; Skrypnik, Aleksandr; Konys, J.

doi:10.1016/j.jnucmat.2017.07.031

Cited by 95 publications

(34 citation statements)

References 47 publications

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“…XRD analysis that the oxide layers of the non-irradiated and irradiated areas composed with both Fe 3 O 4 (Magnetite) and FeCr 2 O 4 (Spinel). It is known that in the case of corrosion in LBE with satisfying enough high oxygen concentration with a range of 10 -4 to 10 -6 wt% and/or longer time typically over than 1000 hours, so-called duplex oxide layer forms on the steel surface [9,28]. The outer layer is Fe 3 O 4 and inner layer is FeCr 2 O 4 in this duplex layers.…”

Section: Lmc Behavior After Irradiationmentioning

confidence: 99%

“…These upper and lower oxygen concentrations are critical values of the oxygen-concentration boundary to be controlled in the ADS. The material corrosion behavior in the LBE has been studied about two decades [8,9] and the corrosion kinetics of T91 was discussed [10]. But, only a few studies [11,12] evaluating irradiation influence on the material properties after the neutron irradiation in LBE have been conducted from the view point of liquid metal embrittlement (LME), not from the liquid metal corrosion (LMC) for irradiated materials.…”

Section: Introductionmentioning

confidence: 99%

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Irradiation Influence on Swelling and Corrosion Behavior of ADS Beam Window Materials, T91 Steels, in Lead Bismuth

Okubo

Fujimura

2020

Proceedings of the 14th International Workshop on Spallation Materials Technology

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In an accelerator driven system (ADS), the beam window material of spallation neutron target will be heavily irradiated under severe conditions, where the displacement damage and high concentrations of helium and hydrogen atom accumulation in the material will occur simultaneously due to high energy spallation neutron and/or proton irradiations in the lead bismuth flow. A main materials issue dedicated to the ADS is the compatibility with the liquid metal of lead bismuth eutectic (LBE), such as liquid metal embrittlement (LME) and liquid metal corrosion (LMC). In this study, we address firstly the swelling behavior of the beam window materials, which is also important for the fuel claddings and connected indirectly with the oxidation reaction induced during irradiation or/and by the irradiation damage. Secondly, the LMC after ion irradiation of ferritic/martensitic steels, T91, are also addressed in the cases of self-ion irradiation and simultaneous irradiation with He and H atoms. The irradiations were performed at temperatures from 350 to 550°C up to 10-40 dpa. In the case of single ion irradiation (only displacement damage), no cavities were observed, but in the cases of dual and triple ion irradiations, many cavities were formed and caused swelling. It was concluded that helium and/or hydrogen enhanced the swelling induced by the simultaneous irradiation case and the peak swelling behavior appeared at an irradiation temperature around 450°C. It was found that, under simultaneous triple ion beams (Fe+He+H), H atoms affected significantly on the swelling development process. Comparing with the dual beams (Fe+He), the enhancement of cavity growth in the deeper region and the suppression of the growth in the medium depth region with changing the number density distributions of cavities might be caused by a fast diffusion of hydrogen atoms. From this result it can be concluded that the swelling of T91 steel depends on the implantation rates of He/dpa and H/dpa. The initial study was originally performed on LMC of T91 steels using the specimen irradiated at 450°C. After the corrosion test at 450°C in the LBE with low oxygen concentration, the surface of the triply irradiated area was covered by the oxide layer even though the non-irradiated area didn't show the enough oxide formation. Therefore, it is concluded that the irradiation can enhance the oxide layer formation supposed due to the two reasons of (1) enhancement of Fe diffusion caused by reducing activation energy of Fe atoms due to helium-vacancy complexes and vacancy clusters after the ion irradiation and (2) enhancement of O interstitial diffusion by radiation defects.

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Section: Lmc Behavior After Irradiationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Irradiation Influence on Swelling and Corrosion Behavior of ADS Beam Window Materials, T91 Steels, in Lead Bismuth

Okubo

Fujimura

2020

Proceedings of the 14th International Workshop on Spallation Materials Technology

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“…The optimal double-layer protective oxide consists of an outer magnetite and inner Cr-Fe spinel layers (Heinzel et al, 2014). Figure 1 summarizes the results of the corrosion exposure tests performed on the AS, and F/M and martensitic steels in LBE containing the required oxygen content at various temperatures, which are available from the literature (Deloffre et al, 2002;Aiello et al, 2004a;Martín et al, 2004;Heinzel et al, 2014;Schroer et al, 2014a,b;Tsisar et al, 2017). General trends can be recognized from the plots: (i) for both types of steels, the tendency to increase the protective oxide layer thickness with increasing temperature of the LBE, and (ii) for F/M and martensitic steels, the increase in the oxide thickness with increased time of exposure, including the tendency to saturation.…”

Section: Introductionmentioning

confidence: 99%

“…However, suitability of the T91 was questioned due to its indicated sensitivity to cracking in HLM, namely, LBE and Pb, based on data from laboratory testing (Nicaise et al, 2001;Auger et al, 2004;Van den Bosch et al, 2006;Di Gabriele et al, 2008;Long & Dai, 2008;Vogt et al, 2008;Coen et al, 2010;Auger et al, 2011;Gorse et al, 2011;Hojná & Di Gabriele, 2011;Gong et al, 2015;Hojná et al, 2015;Stergar et al, 2016;Di Gabriele et al, 2017). (Martín et al, 2004;Heinzel et al, 2014;Schroer et al, 2014b), 304L (Martín et al, 2004), 1.4970 (Heinzel et al, 2014)], F/M (T91, E911 (Aiello et al, 2004a;Schroer et al, 2014a;Tsisar et al, 2017;Yurechko et al, 2018)], and martensitic steels (F82H (Martín et al, 2004), 56T5 (Deloffre et al, 2002)) exposed to LBE as a function of temperature (A) and time (B). The arrow marks the T91 exposed to LBE within creep testing (Yurechko et al, 2018).…”

Section: Introductionmentioning

confidence: 99%

Environmentally assisted cracking of T91 ferritic-martensitic steel in heavy liquid metals

et al. 2020

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In order to advance material development for future nuclear systems, an insight into the cracking conditions of T91 ferritic-martensitic steel in heavy liquid metals (HLM) is provided. The paper critically reviews previous experimental data and summarizes them with new results. The new testing of T91 steel was performed in contact with slow flow and static HLM to study crack initiation, especially in liquid PbBi eutectic at 300°–350°C and Pb at 400°C with about 1 × 10−6 wt.% of oxygen. Pre-stressed coupons were exposed to the liquid metals for up to 2000 h. Constant extension rate tests (CERTs) were performed in the liquid metals to accelerate cracking development. Under static conditions, the testing resulted in oxidation without any crack observation. Under the CERT ones, the T91 steel showed a tendency to crack initiation in PbBi, while in Pb, cracks were not initiated even when the oxide layer was broken. Moreover, the environmentally assisted crack initiated at the maximum load and continued to grow under further loading without unstable failure. Both previous and new data have confirmed that high stress and plastic strain are pre-conditions for the environmentally assisted cracking of T91 in static HLM. It indicates that in the systems utilizing continuous oxygen control of HLM, the LME/EAC of the T91 could develop only in the beyond design load conditions. Further testing is necessary to address the HLM flow speed effect.

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“…Kinetics of corrosion processes of steel components in HLMC is determined by the associated processes of hydrodynamics and the interaction of dissolved components, primarily such as oxygen and iron. The justification and appropriate modeling of these processes is an important component for substantiating heavy liquid metal coolant technology (Robertson et al 1988;Fazio et al 2001;Aiello et al 2004;Ivanov et al 2005Ivanov et al , 2017Zhang et al , 2007Lim et al 2010;Martinelli et al 2008a;Weisenburger 2008;Schroer and Konys 2009;Steiner 2009;Hwang and Lim 2010;Askhadullin et al 2011;Schroer et al 2012;Zhang 2013;Nuclear Energy Agency 2015;Tsisar et al 2017;Salaev et al 2018).…”

Section: Introductionmentioning

confidence: 99%

Basic models and approximation for the engineering description of the kinetics of the oxide layer of steel in a flow of heavy liquid metal coolant under various oxygen conditions

Авдеенков¹,

Achakovsky²,

Ketlerov³

et al. 2020

NUCET

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The article presents the results of corrosion processes, kinetics and changes in the oxide layer modeling using MASKA-LM software complex. The complex is intended for a numerical simulation of three-dimensional non-stationary processes of mass transfer and interaction of impurity components in a heavy liquid metal coolant (HLMC: lead, lead-bismuth). The software complex is based on the numerical solution of coupled three-dimensional equations of hydrodynamics, heat transfer, formation and convective-diffusive transport of chemically interacting components of impurities. Examples of calculations of mass transfer processes and interaction of impurity components in HLMC, formation of protective oxide films on the surfaces of steels are given to justify the coolant technology.

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Characterization of corrosion phenomena and kinetics on T91 ferritic/martensitic steel exposed at 450 and 550 °C to flowing Pb-Bi eutectic with 10−7 mass% dissolved oxygen

Cited by 95 publications

References 47 publications

Irradiation Influence on Swelling and Corrosion Behavior of ADS Beam Window Materials, T91 Steels, in Lead Bismuth

Irradiation Influence on Swelling and Corrosion Behavior of ADS Beam Window Materials, T91 Steels, in Lead Bismuth

Environmentally assisted cracking of T91 ferritic-martensitic steel in heavy liquid metals

Basic models and approximation for the engineering description of the kinetics of the oxide layer of steel in a flow of heavy liquid metal coolant under various oxygen conditions

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