Compatibility of AISI 316 L stainless steel with the Li17Pbg, eutectic

Coen, V.; Fenici, P.; Kolbe, H.; Orecchia, L.; Sasaki, Tsutomu

doi:10.1016/0022-3115(82)90412-3

Cited by 34 publications

(9 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Few data exist on premature failure of 316L induced by liquid metal [7]. So far, only one study was undertaken on the 316L/LBE system [8] and there was little influence of LBE on the fatigue resistance of 316L.…”

Section: Introductionmentioning

confidence: 93%

Susceptibility to LME of 316L and T91 steels by LBE: Effect of strain rate

Hamouche-Hadjem

Auger

Guillot

et al. 2008

Journal of Nuclear Materials

View full text Add to dashboard Cite

Section: Introductionmentioning

confidence: 93%

Susceptibility to LME of 316L and T91 steels by LBE: Effect of strain rate

Hamouche-Hadjem

Auger

Guillot

et al. 2008

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…However, a few relevant papers of previous work on LME in PbLi showed some interesting results. Coen showed that no LME was found for stainless steel 316L at temperatures close to the melting point of lead-lithium [25]. Tests with notched tensile specimens at 350°C under a constant uniaxial tensile load, below the engineering yield stress, however, have evidenced that many cracks filled with Pb and possibly Li were formed, not excluding a liquid metal embrittlement effect [26].…”

Section: Introductionmentioning

confidence: 99%

Liquid metal embrittlement susceptibility of ferritic–martensitic steel in liquid lead alloys

Bosch¹,

Bosch²,

Sapundjiev³

et al. 2008

Journal of Nuclear Materials

View full text Add to dashboard Cite

The susceptibility of the ferritic-martensitic steels T91 and EUROFER97 to liquid metal embrittlement (LME) in lead alloys has been examined under various conditions. T91, which is currently the most promising candidate material for the high temperature components of the future accelerator driven system (ADS) was tested in liquid lead bismuth eutectic (LBE), whereas the reduced activation steel, EUROFER97 which is under consideration to be the structural steel for fusion reactors was tested in liquid lead lithium eutectic. These steels, similar in microstructure and mechanical properties in the unirradiated condition were tested for their susceptibility to LME as function of temperature (150-450°C) and strain rate (1 Â 10 À3 -1 Â 10 À6 s À1 ). Also, the influence of pre-exposure and surface stress concentrators was evaluated for both steels in, respectively, liquid PbBi and PbLi environment. To assess the LME effect, results of the tests in liquid metal environment are compared with tests in air or inert gas environment. Although both unirradiated and irradiated smooth ferritic-martensitic steels do not show any or little deterioration of mechanical properties in liquid lead alloy environment compared to their mechanical properties in gas as function of temperature and strain rate, pre-exposure or the presence of surface stress concentrators does lead to a significant decrease in total elongation for certain test conditions depending on the type of liquid metal environment. The results are discussed in terms of wetting enhanced by liquid metal corrosion or crack initiation processes.

show abstract

“…% Li appears problematical. Corrosion studies performed to date [2][3][4][5] have shown that Pb-17 at. % Li is generally more aggressive than molten lithium, but additional work is required to completely characterize the corrosion processes in lead-lithium and to develop approaches for decreasing its corrosiveness by compositional modifications or by alloy development.…”

Section: Introductionmentioning

confidence: 99%

Corrosion of ferrous alloys exposed to thermally convective Pb-17 at% Li

Tortorelli

DeVan

1986

Journal of Nuclear Materials

View full text Add to dashboard Cite

A type 316 stainless steel thermal convection loop with type 316 stainless steel coupons and a Fe-9 Cr-1 Mo steel loop containing Fe-12 Cr-1 MoVW steel specimens circulated molten Pb-17 at. % Li at a maximum temperature of 500°C. Specimens were exposed for greater than 6000 h. Mass loss and surface characterization data were compared for these two alloys. At any particular exposure time, the corrosion of type 316 stainless steel by Pb-17 at. % Li was more severe, and of a different type than that of similarly exposed Fe-12 Cr-1 MoVW steel. The austenitic alloy suffered nonuniform penetration and dissolution by the lead-lithium, whereas the Fe-12 Cr-1 MoVW steel tended to be more uniformly corroded. The presence of a ferritic layer on the type 316 stainless steel, and its susceptibility to spalling during specimen cleaning, were shown to be important in evaluating the data and in comparing corrosion losses for the two types of alloys. A model for the nonuniform penetration of type 316 stainless steel by Pb-17 at. % Li was suggested. By acceptance of thit article, the I publisher or recipient acknowledge! [ the US. Government's right to retein a nonexclusive, royalty-free license in end to any copyright covering the erticle. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, procsss, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or my agency thereof.

show abstract

Compatibility of AISI 316 L stainless steel with the Li17Pbg, eutectic

Cited by 34 publications

References 1 publication

Susceptibility to LME of 316L and T91 steels by LBE: Effect of strain rate

Susceptibility to LME of 316L and T91 steels by LBE: Effect of strain rate

Liquid metal embrittlement susceptibility of ferritic–martensitic steel in liquid lead alloys

Corrosion of ferrous alloys exposed to thermally convective Pb-17 at% Li

Contact Info

Product

Resources

About