Structural materials for atomic reactors with liquid metal heat-transfer agents in the form of lead or lead—Bismuth alloy

Gorynin, I. V.; Karzov, G. P.; Markov, V. G.; Yakovlev, V. A.

doi:10.1007/bf02469876

Cited by 63 publications

(29 citation statements)

References 2 publications

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“…Weeks and Klamut [12] emphasised that the driving force for the dissolution is the temperature dependence of the solubility of the solid metal in the liquid eutectic. Gorynin et al [1] determined that, for oxygen concentrations lower than 5 · 10 À8 wt%, the austenitic stainless steels undergo in lead at 550°C a dissolution process, whereas at higher oxygen concentrations oxidation occurs preventing dissolution.…”

Section: Discussionmentioning

confidence: 99%

“…It is accepted that austenitic steels may be used in contact with liquid lead-bismuth if the region of operating temperatures is not beyond 400°C. For higher temperatures, martensitic steels are recommended [1]. However, long operation times leads to the dissolution of some elements of the steel (Ni, Cr and Fe, mainly) in the liquid metal and hence some method of protection is needed.…”

Section: Introductionmentioning

confidence: 98%

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Corrosion of stainless steels in lead–bismuth eutectic up to 600 °C

Soler

Martin

Hernández

et al. 2004

Journal of Nuclear Materials

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 98%

Corrosion of stainless steels in lead–bismuth eutectic up to 600 °C

Soler

Martin

Hernández

et al. 2004

Journal of Nuclear Materials

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“…(b) to protect the steel surface by coating or alloying it [5] or by an Ôin situ passive oxidationÕ [6,7]. However, as the phenomena affecting the interactions between a liquid metallic material and a solid substrate depend strongly on the particular system and on the operating conditions, specific investigations have to be performed, helping the compatibility behaviour between the materials to be understood.…”

Section: Introductionmentioning

confidence: 99%

Corrosion behaviour of steels in lead–bismuth at 823 K

Gnecco¹,

Ricci²,

Bottino³

et al. 2004

Journal of Nuclear Materials

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“…Therefore ferritic, ferritic-martensitic (F/M) and oxide dispersion-strengthened (ODS) alloys are better candidates for such applications. It has been shown that the addition of aluminum to the Fe-based ferritic materials is beneficial in preventing corrosion attack and severe oxidation, by forming an Al-rich oxide layer [29][30][31][32][33][34] Generally, the higher the Cr content present, the lower the Al content that is acceptable. Fe-Cr-Al 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 4 alloys display a so-called 'third element effect' (TEE), where Cr (having an oxygen affinity intermediate between those of Fe and Al) is supposed to induce a transition between the internal and external oxidation of Al on ternary alloys under lower Al levels than for binary Fe-Al alloys [37][38][39].…”

Section: Introductionmentioning

confidence: 99%

A study of deformation and strain induced in bulk by the oxide layers formation on a Fe-Cr-Al alloy in high-temperature liquid Pb-Bi eutectic

et al. 2018

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At elevated temperatures, heavy liquid metals and their alloys are known to create a highly corrosive environment that causes irreversible degradation of most iron-based materials. It has been found that an appropriate concentration of oxygen in the liquid alloy can significantly reduce this issue by creating a passivating oxide scale that controls diffusion, especially if Al is present in Fe-based materials (by Al-oxide formation). However, the increase of the temperature and of oxygen content in liquid phase leads to the increase of oxygen diffusion into bulk, and to promotion of the internal Al oxidation. This can cause a strain in bulk near the oxide layer, due either to mismatch between the thermal expansion coefficients of the oxides and bulk material, or to misfit of the crystal lattices (bulk vs. oxides). This work investigates the strain induced into proximal bulk of a Fe-Cr-Al alloy by oxide layers formation in liquid lead-bismuth eutectic utilizing synchrotron X-ray Laue microdiffraction. It is found that internal oxidation is the most likely cause for the strain in the metal rather than thermal expansion mismatch as a two-layer problem.Dear Sir, I re-submit our paper entitled: "A study of deformation and strain induced in bulk by the oxide layers formation on a Fe-Cr-Al alloy in high-temperature liquid Pb-Bi eutectic" on behalf of all co-authors to Acta Materialia, after addressing all the revisions stated by the reviewer. In the study, we analyze a strain in the near-interface bulk of ferritic FeCrAl alloy after its exposure to heavy liquid metals. Two possible origins of strain were considered: internal oxidation of aluminum in bulk, and thermal expansion mismatch between the oxide and the bulk. A positive correlation of dislocation density with peak width distribution indicates that strain comes from plastic deformation, while the evidence of grain refinement and sub-grain formation indicates a noticeable internal oxidation. Based on the comparison with theoretical predictions, we conclude that internal oxidation is more dominant mechanism of strain induction.Sincerely, Miroslav P. Popovic, UC Berkeley Cover LetterWe thank the reviewer for his/her time and effort.Below we address all reviewer's comments (labeled "C") in detail, marked in green (labeled "A").C 0: -Dear authors, congratulations for this interesting work.A 0: We thank the reviewer for his/her assessment of our paper. C1-1: You are studying the deformation and strain induced in the bulk of a Fe-Cr-Al alloy (Alkrothal 720) by oxide scales that form in liquid LBE. Alkrothal is a bcc alloy, a fact that you should clearly mention when you describe the material in the Experimental section (not just mention that it is a ferritic alloy), giving some basic information on the lattice parameters. A1-2: We thank the reviewer for this suggestion. We made changes in the manuscript and modified our statement (in the first paragraph of section 2. Experimental), so it reads now as following: C1-2. What you neglect to mention, however, is th...

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Structural materials for atomic reactors with liquid metal heat-transfer agents in the form of lead or lead—Bismuth alloy

Cited by 63 publications

References 2 publications

Corrosion of stainless steels in lead–bismuth eutectic up to 600 °C

Corrosion of stainless steels in lead–bismuth eutectic up to 600 °C

Corrosion behaviour of steels in lead–bismuth at 823 K

A study of deformation and strain induced in bulk by the oxide layers formation on a Fe-Cr-Al alloy in high-temperature liquid Pb-Bi eutectic

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