Faney et al., 2014 - Google Patents
Spatially dependent cluster dynamics modeling of microstructure evolution in low energy helium irradiated tungstenFaney et al., 2014
- Document ID
- 6435397096023604525
- Author
- Faney T
- Wirth B
- Publication year
- Publication venue
- Modelling and Simulation in Materials Science and Engineering
External Links
Snippet
In fusion reactors, plasma facing components (PFC) and in particular the divertor will be irradiated with high fluxes of low energy (∼ 100 eV) helium and hydrogen ions. Tungsten is one of the leading candidate divertor materials for ITER and DEMO fusion reactors …
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium(0) data:image/svg+xml;base64,PD94bWwgdmVyc2lvbj0nMS4wJyBlbmNvZGluZz0naXNvLTg4NTktMSc/Pgo8c3ZnIHZlcnNpb249JzEuMScgYmFzZVByb2ZpbGU9J2Z1bGwnCiAgICAgICAgICAgICAgeG1sbnM9J2h0dHA6Ly93d3cudzMub3JnLzIwMDAvc3ZnJwogICAgICAgICAgICAgICAgICAgICAgeG1sbnM6cmRraXQ9J2h0dHA6Ly93d3cucmRraXQub3JnL3htbCcKICAgICAgICAgICAgICAgICAgICAgIHhtbG5zOnhsaW5rPSdodHRwOi8vd3d3LnczLm9yZy8xOTk5L3hsaW5rJwogICAgICAgICAgICAgICAgICB4bWw6c3BhY2U9J3ByZXNlcnZlJwp3aWR0aD0nMzAwcHgnIGhlaWdodD0nMzAwcHgnIHZpZXdCb3g9JzAgMCAzMDAgMzAwJz4KPCEtLSBFTkQgT0YgSEVBREVSIC0tPgo8cmVjdCBzdHlsZT0nb3BhY2l0eToxLjA7ZmlsbDojRkZGRkZGO3N0cm9rZTpub25lJyB3aWR0aD0nMzAwLjAnIGhlaWdodD0nMzAwLjAnIHg9JzAuMCcgeT0nMC4wJz4gPC9yZWN0Pgo8dGV4dCB4PScxMzguMCcgeT0nMTcwLjAnIGNsYXNzPSdhdG9tLTAnIHN0eWxlPSdmb250LXNpemU6NDBweDtmb250LXN0eWxlOm5vcm1hbDtmb250LXdlaWdodDpub3JtYWw7ZmlsbC1vcGFjaXR5OjE7c3Ryb2tlOm5vbmU7Zm9udC1mYW1pbHk6c2Fucy1zZXJpZjt0ZXh0LWFuY2hvcjpzdGFydDtmaWxsOiMzQjQxNDMnID5IPC90ZXh0Pgo8dGV4dCB4PScxNjUuNicgeT0nMTcwLjAnIGNsYXNzPSdhdG9tLTAnIHN0eWxlPSdmb250LXNpemU6NDBweDtmb250LXN0eWxlOm5vcm1hbDtmb250LXdlaWdodDpub3JtYWw7ZmlsbC1vcGFjaXR5OjE7c3Ryb2tlOm5vbmU7Zm9udC1mYW1pbHk6c2Fucy1zZXJpZjt0ZXh0LWFuY2hvcjpzdGFydDtmaWxsOiMzQjQxNDMnID5lPC90ZXh0Pgo8L3N2Zz4K data:image/svg+xml;base64,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 [He] 0 title abstract description 88
Classifications
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING; COUNTING
- G06F—ELECTRICAL DIGITAL DATA PROCESSING
- G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
- G06F17/50—Computer-aided design
- G06F17/5009—Computer-aided design using simulation
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Faney et al. | Spatially dependent cluster dynamics modeling of microstructure evolution in low energy helium irradiated tungsten | |
| Nordlund et al. | Multiscale modelling of plasma–wall interactions in fusion reactor conditions | |
| Bonny et al. | Interatomic potential for studying ageing under irradiation in stainless steels: the FeNiCr model alloy | |
| Rymzhanov et al. | Damage threshold and structure of swift heavy ion tracks in Al2O3 | |
| Krasheninnikov et al. | On helium cluster dynamics in tungsten plasma facing components of fusion devices | |
| Faney et al. | Spatially dependent cluster dynamics model of He plasma surface interaction in tungsten for fusion relevant conditions | |
| Schmid et al. | Recent progress in the understanding of H transport and trapping in W | |
| Granberg et al. | Cascade debris overlap mechanism of< 100> dislocation loop formation in Fe and FeCr | |
| Zarkadoula et al. | Electronic effects in high-energy radiation damage in tungsten | |
| Baldwin et al. | Hydrogen isotope transport across tungsten surfaces exposed to a fusion relevant He ion fluence | |
| Hu et al. | Modeling of irradiation hardening of iron after low-dose and low-temperature neutron irradiation | |
| Björkas et al. | Molecules can be sputtered also from pure metals: sputtering of beryllium hydride by fusion plasma–wall interactions | |
| Marian et al. | Modeling fast neutron irradiation damage accumulation in tungsten | |
| Safi et al. | Multi-scale modelling to relate beryllium surface temperature, deuterium concentration and erosion in fusion reactor environment | |
| Dubinko et al. | Dislocation mechanism of deuterium retention in tungsten under plasma implantation | |
| Kim | Primary radiation damage characterization of α-iron under irradiation temperature for various PKA energies | |
| Titus et al. | Impact of electron-captures on nuclei near N= 50 on core-collapse supernovae | |
| Dunn et al. | Simulating radiation damage accumulation in α-Fe: a spatially resolved stochastic cluster dynamics approach | |
| Hodille et al. | Stabilization of defects by the presence of hydrogen in tungsten: simultaneous W-ion damaging and D-atom exposure | |
| Badillo et al. | A phase field model for segregation and precipitation induced by irradiation in alloys | |
| Mathew et al. | Atomistic simulations of helium, hydrogen, and self-interstitial diffusion inside dislocation cores in tungsten | |
| Barton et al. | Model development of plasma implanted hydrogenic diffusion and trapping in ion beam damaged tungsten | |
| Hodille et al. | Kinetic model for hydrogen absorption in tungsten with coverage dependent surface mechanisms | |
| Hodille et al. | Molecular dynamics simulation of beryllium oxide irradiated by deuterium ions: sputtering and reflection | |
| Foley et al. | Quantifying grain boundary damage tolerance with atomistic simulations |