The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys

Cole, James I.; Allen, Todd R.; Was, Gary S.; Dropek, R.; Kenik, E.A.

doi:10.1520/stp11255s

Cited by 8 publications

(8 citation statements)

References 11 publications

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“…Jiao et al [24]mentions that displacement bends are complimentary nucleation positions on behalf of precipitates rich in [Ni]/[Si]. The increase of [Ni] and [Si] with depth, see Figure 8, agrees with our observations made by TEM [22], where the presence of dislocation loops was observed whose density concentration…”

Section: Analysis By X-ray Photoelectron Spectroscopysupporting

confidence: 89%

“…It should be noted that the density of the iron [Fe] is of 7.91 gcm À3 . This steel presented an austenitic structure with lattice parameter a 0 in bulk of 0.35896 nm [22]. The cleaning procedure for the samples is explained in the following lines: (i) a 15 min ultrasonic bath in a trichloroethylene ([C 2 HCl 3 ], 99.9 %, from Sigma-Aldrich Química, S.L.…”

Section: Methodsmentioning

confidence: 99%

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Surface analysis by GXRD and XPS in the austenitic steel DIN by nickel ions

Castañeda

2020

Heliyon

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The composition changes in the close to surface of the austenitic stainless steel DIN 1.4981 irradiated at high doses. Theoretical simulations using the SRIM-2013 program show that the damage due to Nickel cation [Ni 2+ ] ions irradiation of 3.66 MeV extends to up 2 μm deep in the steel under study. Then the applications of Grazing incidence X-ray Diffraction (GXRD) and X-ray Photoelectron Spectroscopy (XPS), Gallium cation [Ga 3+ ] ions sputtering assisted, were necessary to detect respectively, any compositional changes with the depth. GXRD differences were recorded in the intensity and it's Full Width at Half Maximum (FWHM), of the austenite (111) diffraction peak, at different depths in the Irradiate Zone (IZ). Through XPS was found that Nickel [Ni], Niobium [Nb], and Manganese [Mn] were depleted it is important to highlight Chromium [Cr], and Molybdenum [Mo] were improved at the irradiated surface; such behavior was contrary to the element migration under irradiation reported for austenitic stainless steels irradiated at low doses.

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Section: Analysis By X-ray Photoelectron Spectroscopysupporting

confidence: 89%

Section: Methodsmentioning

confidence: 99%

Surface analysis by GXRD and XPS in the austenitic steel DIN by nickel ions

Castañeda

2020

Heliyon

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“…One such APT reconstruction is shown in figure 1a, which shows the level of grain boundary enrichment of these elements. Grain boundary enrichment of Cr was also observed in literature with annealing [8]. No other features are observed by APT in this material.…”

Section: Annealed Samplessupporting

confidence: 86%

Irradiation resistance of a nanostructured 316 austenitic stainless steel

Rajan

Monnet

Hug

et al. 2014

IOP Conf. Ser.: Mater. Sci. Eng.

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High strength state of UFG steel produced by severe plastic deformation N A Enikeev, X Sauvage, M M Abramova et al. -Effect of high pressure torsion on the aging kinetics of -titanium Ti-15Mo alloy Svetlana Gatina, Irina Semenova, Milos Janecek et al. Abstract. The reduction of grain size down to several tens or hundreds of nanometers leads to the enhancement of radiation resistance of metals. Based on this approach, the aim of the Labex EMC3 (Energy Materials and Clean Combustion Center) project "Naninox" is (1) to study the stability of the microstructure of a nanostructured 316 stainless steel under ion irradiation and (2) to link between this microstructure and the properties (corrosion resistance and the microhardness) of the steel (thanks to a better irradiation resistance, a better corrosion resistance and higher mechanical properties after irradiation are expected in the ultra-fine grained stainless steel). Ultrafine grained 316L austenitic stainless steel samples have been produced by high pressure torsion (HPT) at 430˚C and then ion irradiated in Jannus facilities (CEA Saclay) at 450°C and 5 displacements per atoms (dpa). Their microstructure is characterized before and after irradiation by atom probe tomography, X-ray diffraction and transmission electron microscopy. Corrosion behavior in NaCl solution is tested and nano-indentation tests are performed. The first results obtained by atom probe tomography described in this paper indicate that the microstructure of ultrafine grain 316 austenitic stainless steel is more stable under irradiation than the microstructure of a coarse grain 316 austenitic stainless steel.

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“…While the previous study shows the composition gradient that formed from the transient state has an important role in the steady-state microchemistry at defect sinks, Busby et al [17] found that the pre-existing Cr-enrichment at grain boundary due to thermal segregation also leads to the oscillatory behavior of segregation profiles during the subsequent irradiation. Similarly, Cole et al [18] found Cr, Mo and P in 316SS under different cooling rates had already enriched to various levels at grain boundary before the materials being exposed to irradiation environments. The higher the enriched levels lead to the more pronounced W-shape profile during the subsequent irradiation.…”

Section: Introductionmentioning

confidence: 76%

Development of Computational Tools for Predicting Thermal- and Radiation-Induced Solute Segregation at Grain Boundaries in Fe-based Alloys

Yang¹

2016

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Radiation induced segregation (RIS) has been frequently reported in structural materials such as austenitic, ferritic, and ferritic-martensitic stainless steels (SS) that have been widely used in light water reactors (LWRs). RIS has been linked to secondary degradation effects in SS including irradiation induced stress corrosion cracking (IASCC). Earlier studies on thermal segregation in Fe based alloys found that metalloids elements such as P, S, Si, Ge, Sn etc. embrittle the materials when enrichment was observed at grain boundaries (GBs). RIS of Fe-Cr-Ni based austenitic steels has been modeled in the U.S. 2015 fiscal year (FY2015), which identified the pre-enrichment due to thermal segregation can have an important role on the subsequent RIS. The goal of this work is to develop thermal segregation models for alloying elements in steels for future integration with RIS modeling.Thermal segregation and RIS of P in α iron and various steels has been extensively studied and therefore has been chosen as the first element to study. The current approach integrated computational thermodynamics with GB segregation modeling to study thermal equilibrium segregation of solute atoms in α iron in Fe-P, Fe-C-P and Fe-M-P and Fe-M-C-P (M=Cr, Mn, Ni, Mo, Nb, Ti) alloys. The following factors were considered during the modeling: effect of M on the solubility of P in α_Fe; the chemical interaction between Fe-M and M-P; the competition between C and P of GB sites; effect of M on the solubility of C in α_Fe; combined effect of C and M on the P segregation. The major outcomes from this work are:1) Multicomponent thermodynamic database of Fe-M-C-P (M=Cr, Mn, Ni, Mo, Nb, Ti) has been compiled and developed based on critically assessed literature data. This database provided major thermodynamic inputs for thermal GB segregation model.2) The McLean equation was used to describe the GB segregation of an ideal solid solution, and the Guttmann's equation was used to describe the GB segregation of non-ideal solid solution of multicomponent alloys.3) For different alloying additions (M=Cr, Mn, Ni, Mo, Nb, Ti), the solubility of P in α_Fe was systematically evaluated, and the solid solution behavior of Fe-M and M-P was also assessed to provide guidance on the selection of GB segregation model.4) Among the six alloying elements (M=Cr, Mn, Ni, Mo, Nb, Ti), Mn and Ni do not affect the P segregation. The currently used intrinsic segregation energy of Mn and Ni suggests that they do not segregate at GBs. Cr and Mo do not affect the segregation of P either, however, unlike Mn and Ni, they will enrich at GBs due to positive or repulsive interaction with the matrix Fe atoms. Nb and Ti greatly reduces the P segregation due to the very strong scavenging effect. The remaining Nb and Ti in α_Fe are so small that they were not included in GB segregation modeling.5) C strongly affects the P segregation, by competing with P for GB sites. Additions of alloying elements such Cr, Ni, Mn, Mo, Nb and Ti, on one hand, can scavenge the C atoms in solid solution b...

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The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys

Cited by 8 publications

References 11 publications

Surface analysis by GXRD and XPS in the austenitic steel DIN by nickel ions

Surface analysis by GXRD and XPS in the austenitic steel DIN by nickel ions

Irradiation resistance of a nanostructured 316 austenitic stainless steel

Development of Computational Tools for Predicting Thermal- and Radiation-Induced Solute Segregation at Grain Boundaries in Fe-based Alloys

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