On the use of SRIM for computing radiation damage exposure

Stoller, R.E.; Toloczko, Mychailo B.; Was, Gary S.; Certain, Alicia G.; Dwaraknath, Shyam; Garner, F.А.

doi:10.1016/j.nimb.2013.05.008

Cited by 1,238 publications

(410 citation statements)

References 20 publications

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“…The polished surface of the bars were then proton-irradiated at the Michigan Ion Beam Laboratory's 1.7 MeV Tandertron accelerator facility at 2 MeV and 350 ±9 °C to doses of 2.3, 4.7 and 7.0 displacements per atom (dpa) at a current of ~0.2 μA mm -2 , resulting in a damage rate ~6.7 x10 -6 dpa s -1 . The proton irradiation dose (dpa) level was calculated at 60% of the maximum proton penetration depth, 30 μm, calculated by the quick Kinchin-Pease calculation in SRIM as recommended by Stoller et al [26]. As such, TEM foils were prepared for examination at this depth by carefully grinding from the non-irradiated face to a thickness of ~160 μm and then electropolishing using a twin-jet Tenupol-5 electropolisher together with a Julabo FP50 cooling unit.…”

Section: Methodsmentioning

confidence: 99%

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Harte

Topping

Frankel

et al. 2017

Journal of Nuclear Materials

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A. Harte et al., Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy J. Nucl. Mater. Accepted Jan. 2017 Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy (Fe,Ni). This is accomplished through ultra-high spatial resolution scanning transmission electron microscopy and the use of energy-dispersive X-ray spectroscopic methods. Fe-depletion is observed from both SPP types after irradiation with both irradiative species, but is heterogeneous in the case of Zr(Fe,Cr) 2 , predominantly from the edge region, and homogeneously in the case of Zr 2 (Fe,Ni). Further, there is evidence of a delay in the dissolution of the Zr 2 (Fe,Ni) SPP with respect to the Zr(Fe,Cr) 2 . As such, SPP dissolution results in matrix supersaturation with solute under both irradiative species and proton irradiation is considered well suited to emulate the effects of neutron irradiation in this context. The mechanisms of solute redistribution processes from SPPs and the consequences for irradiation-induced growth phenomena are discussed.

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Section: Methodsmentioning

confidence: 99%

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Harte

Topping

Frankel

et al. 2017

Journal of Nuclear Materials

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“…DPA was calculated using the method proposed by Stoller et al [17] using a displacement energy for W of 90 eV [18]. Samples were irradiated using 15 or 60 keV He + ions to achieve He-appm/DPA ratios of ~40,000 and ~2,000, respectively.…”

Section: Methodsmentioning

confidence: 99%

Effect of He-appm/DPA ratio on the damage microstructure of tungsten

Harrison¹,

Amari²,

Greaves³

et al. 2016

MRS Advances

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In-situ ion irradiation and transmission electron microscopy has been used to examine the effects of the He appm to DPA ratio, temperature and dose on the damage structure of tungsten (W). Irradiations were performed with 15 or 60 keV He + ions, achieving He-appm/displacements per atom (DPA) ratios of ~40,000 and ~2000, respectively, at temperatures between 500 and 1000°C to a dose of ~3 DPA. A high number of small dislocation loops with sizes around 5-20 nm and a He bubble lattice were observed for both He-appm/DPA ratios at 500°C with a bubble size ~1.5 nm. Using the g.b=0 criterion the loops were characterised as b = ±1/2<111> type. At 750°C bubbles do not form an ordered array and are larger in size compared to the irradiations at 500°C, with a diameter of ~3 nm. Fewer dislocation loops were observed at this temperature and were also characterised to be b = ±1/2<111> type. At 1000°C, no dislocation loops were observed and bubbles grew as a function of fluence attributed to vacancy mobility being higher and vacancy clusters becoming mobile.

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“…The temperature of the specimens did not increase obviously during ion irradiation by controlling the ion beam intensity (<1 µA). The damage profiles were calculated using the software SRIM 2008, 11,12) as shown in Fig. 1, wherein the displacement energy (E dis ) is 40 eV.…”

Section: Materials and Experimental Proceduresmentioning

confidence: 99%

Nanostructure Variations and Their Effects on Mechanical Strength of Ni-17Mo-7Cr Alloy under Xenon Ion Irradiation

Huang

et al. 2014

Mater. Trans.

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A nickel-base high-temperature alloy (Ni-17Mo-7Cr) has been characterized by nanoindentation and transmission electron microscopy to determine the changes of nanoindentation hardness and microstructural evolution under ion irradiation. Ion irradiation experiments for bulk and thin-foil specimens of Ni-17Mo-7Cr alloy were carried out at room temperature, up to 6.6 dpa, by 7 MeV Xe 26+ and 1 MeV Xe 20+ ions, respectively. The continuous stiffness measurement (CSM) with a diamond Berkovich indent was used to measure the depth profile of hardness. Nanoindentation results for bulk specimens showed an evident ion irradiation induced hardening phenomenon, and the nanoindentation hardness increases with increasing ion dose. High number density of nano-scale black spots and linear-like defects were observed in thin-foil specimens irradiated at 0.33 and 6.6 dpa, respectively. High-resolution transmission electron microscopy images revealed that the black spots were nanoscale solute clusters and dislocation loops, while the linear-like defects were found to be Ni, Mo and Cr-enrichment regions by using the highangle annular dark field-scanning transmission electron microscope. The ion irradiation induced defects can be responsible for the hardening of Ni-17Mo-7Cr alloys.

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On the use of SRIM for computing radiation damage exposure

Cited by 1,238 publications

References 20 publications

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Effect of He-appm/DPA ratio on the damage microstructure of tungsten

Nanostructure Variations and Their Effects on Mechanical Strength of Ni-17Mo-7Cr Alloy under Xenon Ion Irradiation

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