Quick calculation of damage for ion irradiation: implementation in Iradina and comparisons to SRIM

Crocombette, Jean-Paul; Wambeke, Christian Van

doi:10.1051/epjn/2019003

Cited by 60 publications

(27 citation statements)

References 23 publications

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“…The depth profile of the irradiation damage was calculated using Kinchin-Pease mode from the Iradina software (CEA, Saclay, France) [ 15 ] with 40 eV displacement energy. The corresponding irradiation damage profile is presented in Figure 1 a.…”

Section: Methodsmentioning

confidence: 99%

Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

Ribis

Guillou

et al. 2022

Materials

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To improve the safety of nuclear power plants, a Cr protective layer is deposited on zirconium alloys to enhance oxidation resistance of the nuclear fuel cladding during both in-service and hypothetical accidental transients at High Temperature (HT) in Light Water Reactors. The formation of the Cr2O3 film on the coating surface considerably helps in reducing the oxidation kinetics of the zirconium alloy, especially during hypothetic Loss of Coolant Accident (LOCA). However, if the Cr coating is successful to increase the oxidation resistance at HT of the zirconium substrate, for in-service conditions, under neutron irradiation, Cr desquamation has to be avoided to guarantee a safe use of the Cr-coated zirconium alloys. Therefore, the adhesion properties have to be maintained despite the structural defects created by sustained neutron irradiation in the reactor environment. This paper proposes to study the behavior of the Zircaloy-Cr interface of a first generation Cr-coated material during a specific in situ ion irradiation. As deposited, the Cr-coated sample presents a f.c.c. C15 Laves-type intermetallic phase at the interface with off-stoichiometric composition. After irradiation and for the specific conditions applied, this interfacial phase has significantly dissolved. Energy Dispersion Spectroscopy revealed that the dissolution was accompanied by a counterintuitive “sharpening” effect.

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Section: Methodsmentioning

confidence: 99%

Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

Ribis

Guillou

et al. 2022

Materials

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“…Irradiations were performed at room temperature and at 500 • C. At room temperature, the irradiations were conducted using 4000 keV Au 2+ ions with a flux of 2.0 × 10 11 ions•cm −2 s −1 . The depth profile of the irradiation damage was calculated using Kinchin-Pease mode from the Iradina software [14] with 40 eV displacement energy. The irradiation damage profile is presented in Figure 1.…”

Section: Methodsmentioning

confidence: 99%

Nano-Structured Materials under Irradiation: Oxide Dispersion-Strengthened Steels

et al. 2021

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Oxide dispersion-strengthened materials are reinforced by a (Y, Ti, O) nano-oxide dispersion and thus can be considered as nanostructured materials. In this alloy, most of the nanoprecipitates are (Y, Ti, O) nano-oxides exhibiting a Y2Ti2O7 pyrochlore-like structure. However, the lattice structure of the smallest oxides is difficult to determine, but it is likely to be close to the atomic structure of the host matrix. Designed to serve in extreme environments—i.e., a nuclear power plant—the challenge for ODS steels is to preserve the nano-oxide dispersion under irradiation in order to maintain the excellent creep properties of the alloy in the reactor. Under irradiation, the nano-oxides exhibit different behaviour as a function of the temperature. At low temperature, the nano-oxides tend to dissolve owing to the frequent ballistic ejection of the solute atoms. At medium temperature, the thermal diffusion balances the ballistic dissolution, and the nano-oxides display an apparent stability. At high temperature, the nano-oxides start to coarsen, resulting in an increase in their size and a decrease in their number density. If the small nano-oxides coarsen through a radiation-enhanced Ostwald ripening mechanism, some large oxides disappear to the benefit of the small ones through a radiation-induced inverse Ostwald ripening. In conclusion, it is suggested that, under irradiation, the nano-oxide dispersion prevails over dislocations, grain boundaries and free surfaces to remove the point defects created by irradiation.

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“…In the SRIM calculations, a threshold displacement energy of 40 eV was assumed for all the constituent elements. 20 Recent studies 21,22 show that ion-induced damage in both monoatomic and multi-elemental targets with a significant mass difference should be predicted using the full-cascade simulations, as the For 200 keV He ions in NiFe, the conversion factor from ion fluence (10 14 cm -2 ) to peak damage in dpa, based on the full-cascade versus quick TRIM, is 0.0061 or 0.0024 at a depth of ~ 495 nm, respectively.…”

Section: Damage Profile Predictionmentioning

confidence: 99%

Effects of 3d electron configurations on helium bubble formation and void swelling in concentrated solid-solution alloys

et al. 2019

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Elemental specific chemical complexity is known to play a critical role in microstructure development in single-phase concentrated solid-solution alloys (SP-CSAs), including both He bubble formation and irradiation-induced void swelling. While cavity formation and evolution under ion irradiation at elevated temperature are complex nonequilibrium processes, chemical effects are revealed at the level of electrons and atoms herein in a simplified picture, using Ni and a special set of Ni-based SP-CSAs composed of 3d transition metals as model alloys. Based on Ni and model alloys with minimized variables (e.g., atomic mass, size, and lattice structure), we discuss the effects of chemically-biased energy dissipation, defect energetics, sluggish diffusion, and atomic transport on cavity formation and evolution under both self-ion Ni irradiation and He implantation. The observed difference in microstructure evolution is attributed to the effects of d electron interactions in their integrated ability to dissipate radiation energy. The demonstrated impact of alloying 3d transition metals with larger differences in the outermost electron counts suggests a simple design strategy of tuning defect properties for improved radiation tolerance in structural alloys.

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Quick calculation of damage for ion irradiation: implementation in Iradina and comparisons to SRIM

Cited by 60 publications

References 23 publications

Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

Nano-Structured Materials under Irradiation: Oxide Dispersion-Strengthened Steels

Effects of 3d electron configurations on helium bubble formation and void swelling in concentrated solid-solution alloys

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