MeV Au ion irradiation in silicon and nanocrystalline zirconia film deposited on silicon substrate

Chang, Yongqin; Zhang, Yongfeng; Zhu, Zihua; Edmondson, Philip D.; Weber, William J.

doi:10.1016/j.nimb.2012.01.017

Cited by 11 publications

(6 citation statements)

References 21 publications

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“…Parts of the surface were masked so that irradiation‐induced volume swelling could be determined by comparison. The corresponding ion range, ion concentration, and dose in displacements per atom (dpa) were calculated with SRIM 2008.01 full‐cascade simulation code using a density of 6.1 g/cm 3 and threshold displacement energies of 50 eV for both Zr and O atoms . The calculated average range of incident He ions is ~300 nm, and the He/dpa ratio at the peak damage depth is ~2.1 × 10 4 appm/dpa.…”

Section: Methodsmentioning

confidence: 99%

Effects of He Irradiation on Yttria‐Stabilized Zirconia Ceramics

et al. 2014

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Effects of He irradiation on polycrystalline yttria-stabilized zirconia (YSZ) are studied with the focus on irradiation-induced damage buildup, He behavior, and volume swelling. The evolution of irradiation-induced structural damage in polycrystalline YSZ, which is independent of grain orientation, is described by a multistep damage accumulation model. A three-step damage evolution process was found, and different types of defects were observed in the different damage steps. Compared with singlecrystal YSZ, the second damage step occurs at a lower dose in polycrystalline YSZ due to the initial defects and strain. The implanted He ions are readily trapped along the grain boundaries and the mobility of He ions is greatly increased. The enhanced He mobility along the grain boundary leads to a lower threshold irradiation dose and a larger penetration depth for bubble formation. Similar morphologies are observed for the He bubbles in the polycrystalline YSZ and in single-crystal YSZ, and the formation of He bubbles in polycrystalline YSZ is not influenced by grain orientation. As both the extended defects and He bubbles can induce volume swelling, the variation in volume swelling as a function of dose can be divided into a two stage process.

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Section: Methodsmentioning

confidence: 99%

Effects of He Irradiation on Yttria‐Stabilized Zirconia Ceramics

et al. 2014

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“…Innovations in nanostructured materials may yield great gains in radiation resistance 2 3 4 5 due to their high sink strength originating from the large interface-to-volume ratio, as interfaces/surfaces are efficient venues for the trapping and recombination of radiation-induced mobile point/line defects 6 7 . Recently, many experimental and theoretical studies have been dedicated to engineering the radiation tolerance of different kinds of nanostructured nuclear materials, such as nanocrystals 8 9 10 11 12 13 14 , multilayers 15 16 17 18 19 20 21 22 , nanoporous solids 23 24 25 26 , nanowires 27 28 29 30 31 , oxide dispersion strengthened (ODS) steels 32 33 34 35 36 37 , nano-surface reconstruction of plasma-facing materials (PFMs) 38 39 40 and others 41 42 43 . Understanding the radiation response of these materials requires precise knowledge of the primary radiation damage induced in their complex three-dimensional (3D) geometries.…”

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confidence: 99%

IM3D: A parallel Monte Carlo code for efficient simulations of primary radiation displacements and damage in 3D geometry

Yang

Ding

et al. 2015

Sci Rep

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SRIM-like codes have limitations in describing general 3D geometries, for modeling radiation displacements and damage in nanostructured materials. A universal, computationally efficient and massively parallel 3D Monte Carlo code, IM3D, has been developed with excellent parallel scaling performance. IM3D is based on fast indexing of scattering integrals and the SRIM stopping power database, and allows the user a choice of Constructive Solid Geometry (CSG) or Finite Element Triangle Mesh (FETM) method for constructing 3D shapes and microstructures. For 2D films and multilayers, IM3D perfectly reproduces SRIM results, and can be ∼102 times faster in serial execution and > 104 times faster using parallel computation. For 3D problems, it provides a fast approach for analyzing the spatial distributions of primary displacements and defect generation under ion irradiation. Herein we also provide a detailed discussion of our open-source collision cascade physics engine, revealing the true meaning and limitations of the “Quick Kinchin-Pease” and “Full Cascades” options. The issues of femtosecond to picosecond timescales in defining displacement versus damage, the limitation of the displacements per atom (DPA) unit in quantifying radiation damage (such as inadequacy in quantifying degree of chemical mixing), are discussed.

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“…Inspection of data for Ag in Al versus Al in Ag or Au in Al versus Al in Au showed that the SRIM data for electronic stopping of the heavy projectile exceed the light-projectile counterpart by factors up to seven. In support of this finding, Weber and coworkers [7,19,20,21] found that, for Pt, Au and Pb incident on various compound targets at reduced energies between about 0.1 and 50 keV/u, the measured ranges were between 15 and 33% larger than the SRIM derived values.…”

Section: Introductionmentioning

confidence: 77%

“…With ever increasing sophistication of technological development, the number of projectile-target combinations of interest in research and development is increasing steadily, including, for example, less common projectiles like 89 Y [6] or multipurpose ceramics like Zr 2 O [7]. Hence one would ultimately need a data compilation providing access to the stopping and range of any ion in any target of interest.…”

Section: Introductionmentioning

confidence: 99%

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Misconceptions impairing the validity of the stopping power tables in the SRIM library and suggestions for doing better in the future

Wittmaack

2016

Nuclear Instruments and Methods in Physics Research Section B:

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Littmark, which differ from alternative suggestions typically by less than 15%. With this uncertainty, range distributions may be calculated with the TRIM program of SRIM, but only at energies where S n dominates so that uncertainties in S e play a minor role. (vi) As a side aspect, an example is presented illustrating the efforts required to identify incorrect experimental data, notably when respected authors are accountable. (vii) Other approaches to establish stopping power tables are shown to be subject to the same problems as SRIM. It is recommended to add a warning to all theses tables, informing users at which energies the data are likely to lack reliability. (viii) The currently unacceptable quality of S e,f-data below 1 MeV/u could be improved significantly in the future if the user friendly TRIM(SRIM) code were modified to allow simulations with a free choice of nuclear and electronic stopping cross sections. Researchers would thus be enabled to identify optimum input parameters for reproducing measured range distributions at energies at which S n and S e are often of similar magnitude so that their contribution to the total energy loss is difficult to quantify without simulations.

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MeV Au ion irradiation in silicon and nanocrystalline zirconia film deposited on silicon substrate

Cited by 11 publications

References 21 publications

Effects of He Irradiation on Yttria‐Stabilized Zirconia Ceramics

Effects of He Irradiation on Yttria‐Stabilized Zirconia Ceramics

IM3D: A parallel Monte Carlo code for efficient simulations of primary radiation displacements and damage in 3D geometry

Misconceptions impairing the validity of the stopping power tables in the SRIM library and suggestions for doing better in the future

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