On the residual stress profile developed in titanium nitride by ion implantation

Perry, A.J.; Geist, Daniel E.

doi:10.1016/s0168-583x(97)00040-2

Cited by 16 publications

(5 citation statements)

References 12 publications

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“…In this article, we do not focus on radiation damage in the zone of ion path, since we consider a three orders of magnitude more extended zone of exposure due to nanoscale dynamic effects [1,3,31,32] at low radiation doses. As already noted, the role of damage, alloying, and static stresses from embedded impurities should be considered under highdose irradiation [13,14,18,21], when extreme static stresses accumulate, in some cases exceeding the theoretical yield strength of the material. Such stresses are capable of causing the formation of dislocation loops, which are shot into the depth of the substance by tens of micrometers and create in these layers a high density of dislocations that change the properties of the medium.…”

Section: At% Mn)mentioning

confidence: 99%

“…In [2,[4][5][6][7][8], impressive processes of structural-phase transformations with the formation of strongly nonequilibrium states were recorded. There are a large number of examples of the formation of nonequilibrium highly defect states under the action of continuous and powerful pulsed ion beams [9][10][11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26]. In works [1,3,[27][28][29][30][31][32], reverse processes of instantaneous rearrangement of nonequilibrium (metastable) media during ion bombardment at anomalously low temperatures with the transition of these media to states approaching equilibrium as much as possible were found.…”

Section: Introductionmentioning

confidence: 99%

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Structural-and-Phase Transformations in Fe-4.10 and 7.25 at.% Mn Alloys under Intensity External Actions

Ovchinnikov

Makarov

Gushchina

2021

Metals

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The effect of high-pressure torsion (HPT) (P = 8 GPa, e = 5.9) and irradiation with continuous beams of Ar+ ions with energy E = 15 keV on the atomic structure and phase composition of initially quenched iron alloys with 4.10 and 7.25 at.% Mn was studied by the method of Mössbauer spectroscopy. The supersaturated α-solid solution of Fe-7.25 at.% Mn, in contrast to the stable Fe-4.10 at.% Mn, which passes into a highly nonequilibrium metastable state as a result of HPT deformation, is transformed under the influence of ion irradiation at an abnormally low temperature of 280 °C into a two-phase α + γ-state with a highly enriched γ-phase (austenite) (38.4 at.% Mn) and a depleted α-solid solution with 5.76 at.% Mn. The rapid processes with the formation of the γ-phase with a concentration of Mn close to the extrapolation estimate using the equilibrium phase diagram are explained by the cascade radiation shaking of the material by post-cascade powerful elastic and shock waves. Cascade radiation shaking plays the role of temperature and opens up the possibility of achieving states close to equilibrium in the absence of thermally activated processes at record low temperatures.

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Section: At% Mn)mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Structural-and-Phase Transformations in Fe-4.10 and 7.25 at.% Mn Alloys under Intensity External Actions

Ovchinnikov

Makarov

Gushchina

2021

Metals

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“…The work hardening effect was stressed to explain the role of ion implantation as commonly seen in the literature. 18,19) After those reports, development of dense dislocation induced by non-equilibrium penetration of atoms leads to work hardening by micro-strains, or, distortion of original structure by the induced many vacancies, occurs after implantation. If these processes could govern the above self-lubrication mechanism, the similar reduction of wear volume and friction coefficient would be obtained even by using the argon implantation to TiN.…”

Section: Effect Of Self-lubrication On Improvement Of Tribology In Drmentioning

confidence: 99%

Self-Lubrication of Cl-Implanted Titanium Nitride Coating for Dry Metal Forming

2003

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Various kinds of lubricants are utilized in every aspect of manufacturing for mass production. To prolong the life time of tools or dies, much amount of lubricants must be used for mechanical machining or metal forming, resulting in massive emission of wasted lubricants. Dematerialization in the environmentally benign manufacturing requires less use and less emission of lubricants as possible to significantly reduce the environmental burden. For that purpose, dry machining or dry metal forming becomes a challenging issue to be solved. In the present paper, new tribological coating design is proposed to significantly reduce the wear volume and friction coefficient and to minimize the emission of wastes in wear. Titanium nitride coating has been widely used for protection of dies and tools from severe wear. Due to high friction coefficient and less wear endurance, adhesive wear often takes place against the stainless steel or ductile metallic alloy counter parts. Hence, even using this type of protective coating, lubricants are indispensable to reduce the friction coefficient and to be free from metallic sticking. Self-lubrication mechanism can be imprinted into titanium nitride coating only by chlorine implantation into it. Under the presence of chlorine in the wear track, the plastically deforming intermediate oxide film is in-situ formed to sustain low friction and low wearing mode in the relatively wide range of normal pressure and sliding velocity on the contact surface. Through the feasibility study, total amount of chlorine used for this self-lubrication is found to be negligibly small, but the self-lubrication mechanism is sustained to be working until the initial titanium nitride coating is completely worn out from the substrate.

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“…Perry has shown that TiN withstands much radiation damage from argon with 100 keV implant energy and up to 4 × 10 [87,82]. Transmission electron microscope investigations and grazing incidence x-ray diffraction depth profiles showed that, with the implanting of large doses of a heavy ion, the damage profile reaches far beyond the boundaries of displacement damage or implant [88,89,87,86,53,90,91,92,93,94,82,95,96].…”

Section: Radiation Tolerancementioning

confidence: 99%

Radiation Damage and Fission Product Release in Zirconium Nitride

Egeland

2005

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Zirconium nitride is a material of interest to the AFCI program due to some of its particular properties, such as its high melting point, strength and thermal conductivity. It is to be used as an inert matrix or diluent with a nuclear fuel based on transuranics. As such, it must sustain not only high temperatures, but also continuous irradiation from fission and decay products. This study addresses the issues of irradiation damage and fission product retention in zirconium nitride through an assessment of defects that are produced, how they react, and how predictions can be made as to the overall lifespan of the complete nuclear fuel package.Ion irradiation experiments are a standard method for producing radiation damage to a surface for observation. Cryogenic irradiations are performed to produce the maximum accumulation of defects, while elevated temperature irradiations may be used to allow defects to migrate and react to form clusters and loops. Cross-sectional transmission electron microscopy and grazing-incidence x-ray diffractometry were used in evaluating the effects that irradiation has on the crystal structure and microstructure of the material. Other techniques were employed to evaluate physical effects, such as nanoindentation and helium release measurements.Results of the irradiations showed that, at cryogenic temperatures, ZrN withstood over 200 displacements per atom without amorphization. No significant change to the lattice or microstructure was observed. At elevated temperatures, the large amount of damage showed mobility, but did not anneal significantly. Defect clustering was possibly observed, yet the size was too small to evaluate, and bubble formation was not observed.Defects, specifically nitrogen vacancies, affect the mechanical behavior of ZrN dramatically. Current and previous work on dislocations shows a distinct change in slip plane, which is evidence of the bonding characteristics. The stacking-fault energy changes dramatically with lowered nitrogen stoichiometry, resulting in widely spaced partial dislocations in ZrN with high nitrogen vacancy concentration.The wide range of nitrogen stoichiometry in the phase field shows that ZrN may accept nitrogen defects readily. Explanations for this are suggested based upon the bonding structure of these cubic nitrides. This structure allows for a solid framework to remain on one sublattice, while at the same time allowing defects on the other sublattice. This allowance for defects allows significant damage from irradiation yet also decreases the drive for cluster growth. This is evidence that the structure will be acceptable for long-term use as a nuclear reactor fuel.

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On the residual stress profile developed in titanium nitride by ion implantation

Cited by 16 publications

References 12 publications

Structural-and-Phase Transformations in Fe-4.10 and 7.25 at.% Mn Alloys under Intensity External Actions

Structural-and-Phase Transformations in Fe-4.10 and 7.25 at.% Mn Alloys under Intensity External Actions

Self-Lubrication of Cl-Implanted Titanium Nitride Coating for Dry Metal Forming

Radiation Damage and Fission Product Release in Zirconium Nitride

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