A study to compute integrated dpa for neutron and ion irradiation environments using SRIM-2013

Saha, Uttiyoarnab; Devan, K.; Ganesan, S.

doi:10.1016/j.jnucmat.2018.02.039

Cited by 54 publications

(14 citation statements)

References 20 publications

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“…The distribution of the implanted ions and vacancies at equal sample depths was calculated with the use of SRIM programs [25]. which are often used in research of the distribution of ions in the material [26,27,28], and can be used as an input of SRIM codes for systematic analysis of primary radiation damage. Then the Bushehr Nuclear Power Plant (BNPP.…”

Section: Methodsmentioning

confidence: 99%

Comparing of Microhardness of the Stellite 6 Cobalt Alloy Implanted with 175 keV Mn+ Ions and 120 keV N+ Ions

Kamiński¹,

Budzyński²,

Szala³

et al. 2019

Adv. Sci. Technol. Res. J.

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Nowadays, high-precision machines require lightweight materials with very high strength. Ion implantation is used to improve the mechanical strength of the material. A further paper presents the influence of manganese and nitrogen ion implantation on changes of microhardness of the surface layer of cobalt alloy. Samples were analyzed with the SEM-EDS Phenom ProX microscope. Microhardness was assessed with the Vickers method, and the loads of 1 gf (0.00981 N) and 5 gf (0.049 N) was applied using a FM-800 from Future-Tech microhardness meter. At a load of 1 gf, the penetration depth of the implanted specimens was reached not exceeding 0.5 um. At this depth, all samples showed an increase in microhardness compared to the unimplanted sample. The highest increase in microhardness was achieved after implantation of Mn ions with dose D=1•10 17 Mn + /cm 2 and energy E=175 keV. The increased load on the indenter to 5 gf reduced the microhardness differences between implanted and unimplanted samples.

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Section: Methodsmentioning

confidence: 99%

Comparing of Microhardness of the Stellite 6 Cobalt Alloy Implanted with 175 keV Mn+ Ions and 120 keV N+ Ions

Kamiński¹,

Budzyński²,

Szala³

et al. 2019

Adv. Sci. Technol. Res. J.

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“…Alternatively, this energy can be calculated from BCA simulations which describes the energy imparted to the material by the PKA as a function of depth [14]. In principle the total damage produced by a neutron flux can be calculated with a set of BCA simulations: one set for every PKA species and for every PKA energy that is created by the neutron flux, with the results summed and weighted accordingly [24,25]. For a homogeneous single-phase material, this is a large but feasible set of calculations.…”

Section: Theoretical Frameworkmentioning

confidence: 99%

Spatial Distribution of Primary Radiation Damage in Microstructures

Burr

Brand

Obbard

2022

Preprint

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The universally-used theory of Norgett, Robinson and Torrens (NRT) for calculating primary radiation damage in materials assumes that materials are homogeneous. For many engineering materials, which have rich microstructures, this assumption is poor. As there are no alternative radiation damage theories that include heterogeneity, the role of the microstructure on primary radiation damage has been neglected. Here we extend the NRT formalism to account for microstructural variations and account for the damage caused in a phase by primary knock-on atoms that are produced in another nearby phase. The new approach converges to conventional NRT at suitably large length-scales, and agrees with binary collision approximation simulations for individual phases of a microstructure. Applying the method to a ferritic superalloy, we show that the damage can vary by up to 30% from one phase to another, and up to 7% within a single phase. Substantially greater variations are predicted for more chemically heterogeneous alloys. Our new approach provides new physical insight into the interplay between microstructure and primary radiation damage.

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“…where x is the depth of implanted helium-3 ions, with unit Å; N(x) is the amount of implanted helium-3 ions per unit volume at depth x, with unit 1/Å 3 ; D is the dose of incident helium-3 ions, with unit ions/Å 2 ; R p is the mean projected range of all ions on the x axis, with unit Å; ∆R p is the corresponding standard error, with unit Å. The energy transfer of incident helium-3 ions is shown in Equation (3) [37]:…”

Section: Theoretical Model About Implantation Of Helium-3 Into Ilmenitementioning

confidence: 99%

Theoretical Study on Thermal Release of Helium-3 in Lunar Ilmenite

et al. 2021

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The in-situ utilization of lunar helium-3 resource is crucial to manned lunar landings and lunar base construction. Ilmenite was selected as the representative mineral which preserves most of the helium-3 in lunar soil. The implantation of helium-3 ions into ilmenite was simulated to figure out the concentration profile of helium-3 trapped in lunar ilmenite. Based on the obtained concentration profile, the thermal release model for molecular dynamics was established to investigate the diffusion and release of helium-3 in ilmenite. The optimal heating temperature, the diffusion coefficient, and the release rate of helium-3 were analyzed. The heating time of helium-3 in lunar ilmenite under actual lunar conditions was also studied using similitude analysis. The results show that after the implantation of helium-3 into lunar ilmenite, it is mainly trapped in vacancies and interstitials of ilmenite crystal and the corresponding concentration profile follows a Gaussian distribution. As the heating temperature rises, the cumulative amounts of released helium-3 increase rapidly at first and then tend to stabilize. The optimal heating temperature of helium-3 is about 1000 K and the corresponding cumulative release amount is about 74%. The diffusion coefficient and activation energy of helium-3 increase with the temperature. When the energy of helium-3 is higher than the binding energy of the ilmenite lattice, the helium-3 is released rapidly on the microscale. Furthermore, when the heating temperature increases, the heating time for thermal release of helium-3 under actual lunar conditions decreases. For the optimal heating temperature of 1000 K, the thermal release time of helium-3 is about 1 s. The research could provide a theoretical basis for in-situ helium-3 resources utilization on the moon.

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A study to compute integrated dpa for neutron and ion irradiation environments using SRIM-2013

Cited by 54 publications

References 20 publications

Comparing of Microhardness of the Stellite 6 Cobalt Alloy Implanted with 175 keV Mn+ Ions and 120 keV N+ Ions

Comparing of Microhardness of the Stellite 6 Cobalt Alloy Implanted with 175 keV Mn+ Ions and 120 keV N+ Ions

Spatial Distribution of Primary Radiation Damage in Microstructures

Theoretical Study on Thermal Release of Helium-3 in Lunar Ilmenite

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