Long-term service of austenitic steel 1.4571 as a container material for flowing lead–bismuth eutectic

Schroer, Carsten; Wedemeyer, Olaf; Novotný, Josef; Skrypnik, Aleksandr; Konys, J.

doi:10.1016/j.jnucmat.2011.07.026

Cited by 45 publications

(23 citation statements)

References 12 publications

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“…In both cases the near-surface zone of the steel does not show depletion in steel constituents beyond the corrosion front. Similar corrosion appearances were observed in LBE with 10 À6 mass% dissolved oxygen, but as a result of local failure of spinel layer (AO), representing general corrosion mode, or Cr-based oxide film (PS) [5,17,18]. Both, selective and non-selective leaching are governed by the transport of solved elements in the boundary layer and subsequent transfer to the liquid metal bulk [6].…”

Section: Corrosion Appearances Observedmentioning

confidence: 86%

“…In contrast, 316L is in solutionannealed state. A detailed discussion on differences in composition and structure of these steels as well as samples preparation and description of CORRIDA loop operated at the Karlsruhe Institute of Technology (KIT) are presented elsewhere [18,19].…”

Section: Methodsmentioning

confidence: 99%

“…At 10 À6 mass% dissolved oxygen, the austenitic steels mostly show AO accompanied by spinel formation [5,17,18]. With time, after local failure of scale, a local SBA via selective leaching occurs.…”

Section: Introductionmentioning

confidence: 99%

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Long-term corrosion of austenitic steels in flowing LBE at 400 °C and 10 −7 mass% dissolved oxygen in comparison with 450 and 550 °C

Tsisar

Schroer

Wedemeyer

et al. 2016

Journal of Nuclear Materials

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Section: Corrosion Appearances Observedmentioning

confidence: 86%

Section: Methodsmentioning

confidence: 99%

See 1 more Smart Citation

Long-term corrosion of austenitic steels in flowing LBE at 400 °C and 10 −7 mass% dissolved oxygen in comparison with 450 and 550 °C

Tsisar

Schroer

Wedemeyer

et al. 2016

Journal of Nuclear Materials

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“…Using these facilities, various experimental campaigns were conducted. Ther esults have contributed to the mechanistic understandingand production of quantitative data on the performanceo ft he typical ferritic-martensitic [44][45][46][47][48][49] and austenitic steels [30,45,[50][51][52][53][54][55][56] as well as oxide-dispersion strengthened (ODS) steels. [57][58][59] Furthermore,t he effects of adding aluminum (Al) [60][61][62][63][64] and silicon( Si) [59] to steels were addressed.…”

Section: Corrosion and Corrosion Protection In Liquid-metal Systemsmentioning

confidence: 99%

Liquid Metals as Efficient High‐Temperature Heat‐Transport Fluids

et al. 2017

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Liquid metals appear to be attractive heat‐transport fluids, in particular if looking at their high thermal conductivities and low viscosities. Despite some pioneering technical applications in the past, complex handling, special requirements, safety concerns, and structural degradation of the materials have prevented their widespread application. However, progress in research and development on liquid‐metal science and technology has advanced considerably in the last decade, and this has opened the gate to their broader use in the short term. This requires a more differentiated view on liquid metals, particularly on the specific properties of individual fluids within the context of specific applications. By doing so, many commonly mentioned prejudices vanish or are of minor significance. At the Karlsruhe Institute of Technology, a comprehensive research program on liquid‐metal technology has been pursued for more than 50 years, and some of the advances in different applications will be outlined in this article.

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“…[35] Recent studies have focused on tests of characterizing the properties of the oxide layer formed in LBE environments and finding techniques to enhance the protective efficiency. Other long-term tests include tests on Fe10CrAl alloys, [58] 1.4571 steel, [59] and pure Fe. Short-term tests have been conducted on potential structure steels such as 316 (e.g., [43,44] ), 316L (e.g., [45,46] ), 304L (e.g., [47,48] ), 1.4790 (e.g., [49,50] ), D-9 (e.g., [51] ).…”

Section: Lbe Corrosionmentioning

confidence: 99%

Lead–Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts

Zhang

2013

Adv Eng Mater

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LBE is one of the primary coolant candidates of advanced nuclear reactors. The present review conducts an assessment of the coolant based on a series of liquid metal coolant selection criteria first and then identifies the key concerns of using LBE as the primary coolant of a nuclear reactor. The review focuses on the status of the art of these key concerns: materials degradation, protective oxide layer, and polonium production and control in an LBE coolant system. The review also addresses oxidation kinetics of steels in oxygen-containing LBE, development of oxygen technology and comparisons between LBE and liquid sodium.

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Long-term service of austenitic steel 1.4571 as a container material for flowing lead–bismuth eutectic

Cited by 45 publications

References 12 publications

Long-term corrosion of austenitic steels in flowing LBE at 400 °C and 10 −7 mass% dissolved oxygen in comparison with 450 and 550 °C

Long-term corrosion of austenitic steels in flowing LBE at 400 °C and 10 −7 mass% dissolved oxygen in comparison with 450 and 550 °C

Liquid Metals as Efficient High‐Temperature Heat‐Transport Fluids

Lead–Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts

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