Effects of temperature and strain rate on the tensile behaviors of SIMP steel in static lead bismuth eutectic

Liu, Jian; Yan, Wei; Sha, Wei; Wang, Wei; Shan, Yiyin; Yang, Ke

doi:10.1016/j.jnucmat.2016.02.032

Cited by 25 publications

(9 citation statements)

References 30 publications

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“…For steels tempered at 760 • C (HT760), the LME susceptibility was severe in the 300-450 • C range, while more severe LME effects were observed when the tempering heat treatment was performed at 600 • C (HT600) and 500 • C (HT500), as evidenced by the existence of both wider and deeper "ductility troughs". A similar "ductility trough" was also observed in Si-enriched ferritic steels [251,501]. This also bears similarity with the findings of Abramov et al regarding an Fe-12Cr-Mo ferritic steel in contact with liquid Pb [360].…”

Section: The Role Of Temperaturesupporting

confidence: 89%

“…The shape of the "ductility trough" was also reported to depend on the applied strain rate [501,535]. It was found by Liu et al…”

Section: The Role Of Strain Ratementioning

confidence: 91%

“…The second category relates to the dependence on the steel metallurgical state [458,471] and its alteration under irradiation [45,493,[496][497][498]. The third category ("kinetic" factors) includes the temperature [447,457,458,471,493,494,[499][500][501], the applied strain/loading rate [306,478,493,494,[501][502][503], and, to some extent, the HLM oxygen concentration [493,502,504]. The mechanical testing standard used to investigate LME until the 1990s has almost exclusively focused on either tensile testing or fatigue testing.…”

Section: Factors Affecting the Lme Of F/m Steels In Liquid Pb/lbementioning

confidence: 99%

See 2 more Smart Citations

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

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et al. 2022

Progress in Materials Science

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Section: The Role Of Temperaturesupporting

confidence: 89%

“…The shape of the "ductility trough" was also reported to depend on the applied strain rate [501,535]. It was found by Liu et al…”

Section: The Role Of Strain Ratementioning

confidence: 91%

Section: Factors Affecting the Lme Of F/m Steels In Liquid Pb/lbementioning

confidence: 99%

See 1 more Smart Citation

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Gong

Short

Auger

et al. 2022

Progress in Materials Science

189

View full text Add to dashboard Cite

“…In the literature, the ductility trough, which is typical for LME, indicates the loss of ductility as a function of temperature for different strain rates [ 34 , 35 , 36 ]. In this study, the most pronounced LME can be found at tests with low strain rates and high temperatures, which indicates that liquid zinc shows a limited wetting speed at the crack tip.…”

Section: Resultsmentioning

confidence: 99%

Liquid Metal Embrittlement of Advanced High Strength Steel: Experiments and Damage Modeling

et al. 2021

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In the automotive industry, corrosion protected galvanized advanced high strength steels with high ductility (AHSS-HD) gain importance due to their good formability and their lightweight potential. Unfortunately, under specific thermomechanical loading conditions such as during resistance spot welding galvanized, AHSS-HD sheets tend to show liquid metal embrittlement (LME). LME is an intergranular decohesion phenomenon leading to a drastic loss of ductility of up to 95%. The occurrence of LME for a given galvanized material mainly depends on thermal and mechanical loading. These influences are investigated for a dual phase steel with an ultimate tensile strength of 1200 MPa, a fracture strain of 14% and high ductility (DP1200HD) by means of systematic isothermal hot tensile testing on a Gleeble® 3800 thermomechanical simulator. Based on the experimental findings, a machine learning procedure using symbolic regression is applied to calibrate an LME damage model that accounts for the governing quantities of temperature, plastic strain and strain rate. The finite element (FE) implementation of the damage model is validated based on the local damage distribution in the hot tensile tested samples and in an exemplary 2-sheet resistance spot weld. The developed LME damage model predicts the local position and the local intensity of liquid metal induced cracking in both cases very well.

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“…Due to its a low melting point, low vapor pressure, high atomic number and high thermal conductivity, lead-bismuth eutectic (LBE) is considered the primary candidate material used in spallation target and coolant. One of the serious problems using LBE is that containment materials, such as ferritic-martensitic (FM) steels, suffer from LBE corrosion [ 2 , 3 ]. Oxidation, dissolved corrosion and liquid metal embrittlement possible occur when FM steels contact with LBE.…”

Section: Introductionmentioning

confidence: 99%

Comparison between Subsequent Irradiation and Co-Irradiation into SIMP Steel

et al. 2021

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A modern Chinese ferritic/martensitic steel SIMP, is a new perspective nuclear structural material for the spallation target in accelerator driven sub-critical system. In this work, aimed at exploring the radiation resistance properties of this material, we investigate the differences between simultaneous Fe and He ions irradiation and He implantation of SIMP steel pre-irradiated by Fe self-ions. The irradiations were performed at 300 °C. The radiation-induced hardening was evaluated by nano-indentation, while the lattice disorder was investigated by transmission electron microscopy. Clear differences were found in the material microstructure after the two kinds of the ion irradiation performed. Helium cavities were observed in the co-irradiated SIMP steel, but not the case of He implantation with Fe pre-irradiation. In the same time, the size and density of Frank loops were different in the two different irradiation conditions. The reason for the different observed lattice disorders is discussed.

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Effects of temperature and strain rate on the tensile behaviors of SIMP steel in static lead bismuth eutectic

Cited by 25 publications

References 30 publications

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Liquid Metal Embrittlement of Advanced High Strength Steel: Experiments and Damage Modeling

Comparison between Subsequent Irradiation and Co-Irradiation into SIMP Steel

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