Corrosion investigations of steels in flowing lead at 400°C and 550°C

Glasbrenner, H.; Konys, J.; Mueller, Georg; Rusanov, A. E.

doi:10.1016/s0022-3115(01)00522-0

Cited by 75 publications

(47 citation statements)

References 6 publications

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“…Consequently, corrosion occurs easily, especially at grain boundaries. The 773-1073 K temperature range is particularly prone to carbide enhanced corrosion: at lower temperatures, neither carbon nor chromium migrates very rapidly, while at high temperatures, both carbon and chromium can migrate, and thus chromium can be replenished at the metal surface [3].…”

Section: Discussionmentioning

confidence: 99%

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Spectroscopic and microscopic investigation of the corrosion of 316/316L stainless steel by lead–bismuth eutectic (LBE) at elevated temperatures: importance of surface preparation

Johnson

Parsons

Manzerova

et al. 2004

Journal of Nuclear Materials

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The corrosion of steel by lead-bismuth eutectic (LBE) is an important issue in proposed nuclear transmutation schemes. Steel samples were exposed to oxygen-controlled LBE at high temperature and exposure times that simulate actual reactor systems. Scanning electron microscopy (SEM), combined with energy-dispersive X-ray analysis (EDAX) and X-ray photoelectron spectroscopy (XPS), has been used to study post-exposure steel samples and unexposed controls. Our investigation of the reacted samples revealed preferential segregation of metals contained in the initial alloy formulations. Sputter depth profiling of the exposed annealed sample and cold-rolled sample showed a marked difference in oxide layer composition, depending on surface preparation. The annealed sample showed a complex oxide structure (iron oxide over chromium/iron oxide mixtures) of tens of microns thickness. The cold-rolled sample was covered with a rather simple, primarily chromium oxide layer of ~1 micron thickness. The cold-rolled sample had an order of magnitude less corrosion (i.e., both lower oxidation and less weight change) than the annealed sample.3

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Section: Discussionmentioning

confidence: 99%

“…Ghetta et al [2] designed a detailed and precise description for procedures for corrosion studies of steel samples in molten lead. Glasbrenner et al [3] conducted corrosion studies of steels in flowing lead at temperatures of 673 K and 823 K.…”

Section: Introductionmentioning

confidence: 99%

Spectroscopic and microscopic investigation of the corrosion of 316/316L stainless steel by lead–bismuth eutectic (LBE) at elevated temperatures: importance of surface preparation

Johnson

Parsons

Manzerova

et al. 2004

Journal of Nuclear Materials

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“…The primary factor limiting the technological viability of the Pb and Pb-Bi eutectic is their corrosive nature towards structural steels. Such coolant has tendency to corrode/dissolute alloying elements from the fuel cladding and structural materials [1,[5][6][7][8][9] within the reactor and causes liquid metal embrittlement (LME) [1,[10][11][12][13][14]. Oxide scales are known to be able to protect the structural alloys against the liquid metal corrosion [1,7].…”

Section: Introductionmentioning

confidence: 99%

“…Such coolant has tendency to corrode/dissolute alloying elements from the fuel cladding and structural materials [1,[5][6][7][8][9] within the reactor and causes liquid metal embrittlement (LME) [1,[10][11][12][13][14]. Oxide scales are known to be able to protect the structural alloys against the liquid metal corrosion [1,7]. The stability of this surface barrier and its long-term protective properties depend on the oxygen content in the environment (coolant) and mainly on the composition and microstructure of the exposed steel [15][16][17][18].…”

Section: Introductionmentioning

confidence: 99%

Characterisation of Oxides by Advanced Techniques

Duchoň

Halodová

Lorincink

et al. 2018

Acta Metall. Slovaca

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For the safe development of GenIV nuclear reactors, it is necessary to study the compatibility of structural materials with new coolants. Current work describes the behavior of ferriticmartensitic steel T91 in a Heavy Liquid Metal environment. Specimens were pre-stressed up to yield strength and subsequently exposed to the lead-bismuth eutectic (LBE) under static conditions for 2000 hours. The goal was to identify the susceptibility to crack initiation under selected experimental conditions. The examination of metal-LBE interface was done in a reference position of the sample using the SEM equipped with EDX. Formation of oxide scales observed on the interface had no signs of crack initiation. The oxide was characterized by a twolayer structure. A TEM lamella was created from the sample by a FIB in-situ lift-out technique and it was subsequently analyzed in HRTEM. Individual oxide layers were identified and characterized by SAED, EELS and EDS techniques. Finally, STEM-HAADF and EFTEM techniques were used to visualize the matrix-oxide interface.

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“…Pb or Pb-Bi is also the spallation material and coolant. Further details and references are given in Knebel (2002) and Glasbrenner (2001). The KArlsruhe Lead LAboratory (KALLA) is one of the few European Pb facilities conducting experiments on Pb/Pb-Bi coolant flow, corrosion, and spallation materials.…”

Section: Germany: Forschungszentrum Karlsruhementioning

confidence: 99%

Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

Khericha¹

2006

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Corrosion investigations of steels in flowing lead at 400°C and 550°C

Cited by 75 publications

References 6 publications

Spectroscopic and microscopic investigation of the corrosion of 316/316L stainless steel by lead–bismuth eutectic (LBE) at elevated temperatures: importance of surface preparation

Spectroscopic and microscopic investigation of the corrosion of 316/316L stainless steel by lead–bismuth eutectic (LBE) at elevated temperatures: importance of surface preparation

Characterisation of Oxides by Advanced Techniques

Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

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