-
UKAEA-CCFE-PR(25)3082025
-
UKAEA-CCFE-PR(25)3952024
Measurements of lattice strain at high spatial resolution are becoming accessible and routine, owing to advances in imaging techniques such as 4D Scanning Transmission Electron Microscopy. This has the potential to enhance materials characterisation, but the data are difficult to interpret. We present a procedure for extracting local concentrations…
-
UKAEA-CCFE-PR(25)3922024
The occurrence of high stress concentrations in reactor components is a still intractable phenomenon encountered in fusion reactor design. We observe and quantitatively model a non-linear high-dose radiation mediated microstructure evolution effect that facilitates fast stress relaxation in the most challenging low-temperature limit. In situ…
-
UKAEA-CCFE-PR(25)3842024
Radiation creep and swelling are the macroscopic irreversible deformation phenomena, occurring in materials exposed to energetic particle irradiation even at low temperatures. On the microscopic scale, energetic particles initiate collision cascades, generating and…
-
UKAEA-CCFE-PR(25)3482024
Determining stress and strain in a component of a fusion power plant involves defining boundary conditions for the mechanical equilibrium equations, implying the availability of a full reactor model for defining those conditions. To address this fundamental challenge of reactor design, a finite element method (FEM) model for the Mega-Ampere Spheric…
-
UKAEA-CCFE-PR(25)3892023
Swelling and microstructural evolution of nanocrystalline (NC) tungsten are investigated by atomic scale simulations exploring the low temperature, high radiation exposure limit. Statistical analysis of microstructures containing at least a million atoms, with the grain size varying from 5 nm to 20 nm, suggests that their evolution is dominated …
-
UKAEA-CCFE-PR(24)2262023
Fusion reactor components will be exposed to fluxes of high energy neutrons while also being subjected to thermal, mechanical and magnetic loads. Exposure to neutron irradiation has numerous consequences, including swelling a…
-
UKAEA-CCFE-PR(23)1722023
Neutrons interacting with atomic nuclei in most of the materials included in the current fusion reactor designs—notably tungsten, ferritic and stainless steels, copper alloys—generate a γ-photon flux that is comparable in magnitude and e…
-
UKAEA-CCFE-PR(23)1712023
We simulate effects of irradiation on nanocrystalline tungsten in the athermal high dose limit using the creation-relaxation algorithm, where microstructural evolution is driven not by thermally activated diffusion, but by fluctuating stresses resulting from the production and relaxation of defects. Over the entire interval of radiation exposure sp…
-
UKAEA-CCFE-PR(24)2442022
Zirconium alloys are widely used as the fuel cladding material in pressurised water reactors where a significant population of defects and dislocations is produced by exposure to neutrons. We present and interpret synchrotron microbeam X-ray diffraction measurements of proton- irradiated Zircaloy-4, where we identify a transient peak and the sub…
Showing 1 - 10 of 121 UKAEA Paper Results