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UKAEA-CCFE-CP(18)072018
This paper addresses the EUROfusion DEMO materials research program and highlights the characterization of the in-vessel baseline materials EUROFER97, CuCrZr and tungsten as well as advanced structural and high heat flux materials developed for risk mitigation. In support of engineering design activities the focus primarily is to assemble a data ba…
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UKAEA-CCFE-PR(18)832018
Magnetic plasma confinement is a key element of fusion tokamak power plant design, yet changes in magnetic properties of alloys and steels occurring under neutron irradiation are often overlooked. We perform a quantitative study exploring how irradiation-induced precipitation affects magnetic properties of Fe-Cr alloys. Magnetic properties are simu…
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UKAEA-CCFE-PR(18)722018
Formation and migration energies, elastic dipole and relaxation volume tensors of nano-defects are the parameters that determine the rates of evolution of microstructure under irradiation and the magnitude of macroscopic elastic stresses and strains resulting from the accumulation of defects in materials. To find accurate values of these parameters…
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UKAEA-CCFE-PR(18)492018
Predicting strains, stresses and swelling in power plant components exposed to irradiation directly from the observed or computed defect and dislocation microstructure is a fundamental problem of fusion power plant design that has so far eluded a practical solution. We develop a model, free from parameters not accessible to direct evaluation or obs…
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UKAEA-CCFE-PR(18)382018
Conventional linear elasticity theory predicts the strain fields of a dislocation core to diverge, whereas it is known from atomistic simulations that strains at dislocation cores remain finite. We present an analytical solution to a generalised, variational Peierls-Nabarro model of edge dislocation displacement fields that features a finite core w…
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UKAEA-CCFE-PR(18)302018
We present a new analysis of nanoscale lattice defects observed after low-dose in situ self-ion irradiation of tungsten foils at cryogenic temperature. For decades, defect counts and size-frequency histograms have been the standard form of presenting a quantitative analysis of the nanoscale “black-dot” damage typical of such irradiations. Here …
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UKAEA-CCFE-PR(18)252018
The evolution of the defect microstructure in materials at high temperature is dominated by diffusion-mediated interactions between dislocations, vacancy clusters and surfaces. This gives rise to complex non-linear couplings between interstitial and vacancy-type dislocation loops, cavities and the field of diffusing vacancies that adiabatically fol…
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UKAEA-CCFE-PR(18)72018
The line tension model of obstacle hardening is modified to account for the thermally activated, kink-limited glide of 1=2h111i screw dislocations, allowing application to the plastic flow of bcc metals. Using atomistically-informed dislocation mobility laws, Frenkel-Kontorova simulations and a simplified dislocation obstacle model, we identify a …
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CCFE-PR(17)692017
Density functional theory (DFT) calculations show that self-interstitial atom defects in nonmagnetic body-centred cubic (bcc) metals adopt strongly anisotropic configurations, elongated in the h111i direction1–4. Elastic distortions, associated with such anisotropic defect configurations, appear similar to the distortions around small prismatic d…
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CCFE-PR(17)642017
In a fusion tokamak, the plasma of hydrogen isotopes is in contact with tungsten at the surface of a divertor. In the bulk of the material, the hydrogen concentration profile tends towards dynamic equilibrium between the flux of incident ions and their trapping and release from defects, either native or produced by ion and neutron irradiation. The …
Showing 41 - 50 of 116 UKAEA Paper Results