-
UKAEA-CCFE-PR(25)2902023
The augmentation of mechanical properties of reduced activation ferritic martensitic steels through the introduction of creep resistant nano-oxide particles produces a class of oxide dispersion strengthened steels, which have attracted significant interest as candidates for first wall supporting structural materials in future nuclear fusion reac…
-
UKAEA-CCFE-PR(25)2842023
Nuclear fusion is a potential source of electricity which can address the environmental problems posed by fossil fuels. Eurofer97 steel is a primary structural material for breeding blanket and divertorcomponents in fusion Tokamaks.. Assembling and maintaining the structural integrity of these in-vessel components requires remote joint technique…
-
UKAEA-CCFE-CP(25)022022
Within the EU-DEMO first wall protection framework, work on limiter’s plasma-facing component design has started under plasma disruptive events (Richiusa et al., 2022). Starting from the rationale behind the TARTIFL&TTE software (Richiusa et al., 2022), this companion paper describes the progress on the engineering modelling of the plasma-facing …
-
UKAEA-CCFE-PR(25)2762024
Creep-fatigue damage has been recognised as a critical failure mode for high-temperature structures. In fusion power reactors, plasma-facing components endure complex loading conditions, resulting in high thermomechanical stresses. These components, often made from 316L material, joined to ferritic-martensitic steels, face significant challenges…
-
UKAEA-CCFE-PR(25)2752021
Several fusion power concepts propose the use of liquid lithium as the primary coolant and tritium breeder. Conventional Heat Exchangers (HEX) use water. In order to avoid tritium permeation into water, a molten salt can be used as secondary coolant, with water as the tertiary system. Nevertheless, the design of the HEX to transfer the energy fr…
-
UKAEA-CCFE-PR(25)2662024
This paper reports on a FEM-based computational methodology to assess dynamic amplification factors (DAF) of a divertor cassette, under electromagnetic (EM) impact loads caused by a plasma disruption event. The investigation concerns a typical divertor cassette body (CB) of the European DEMO reactor (baselin…
-
UKAEA-CCFE-PR(25)2652025
The development of discrete strain at the microstructural scale during the onset of plasticity is potentially linked to fatigue crack nucleation in engineering alloys. Hence, quantifying such discrete strain and its evolution is a pathway to understand the microstructural influence on fatigue crack nucleation and to develop crack initiation mode…
-
UKAEA-CCFE-PR(25)2722025
The development and distribution of microscopic shear strain have been investigated using high-resolution digital image correlation at the onset of plastic deformation in face-centred cubic CoCrFeNi high entropy al- loys with different grain sizes. Microscopic strain localisation increased with grain size as shown by the presence of planar slip …
-
UKAEA-CCFE-PR(24)2542023
Conventional crystal plasticity (CP) solvers are based on a Newton-Raphson (NR) approach which use an initial guess for the free variables (often stress) to be solved. These solvers are limited by a finite interval of convergence and often fail when the free variable falls outside this interval. Solution failure results in the reduction of the t…
-
UKAEA-CCFE-PR(24)2352024
Engineering components within a fusion reactor are subjected to extreme environments including high heat flux, strong magnetic fields, and neutron irradiation. Simulations are required to predict the in-service lifetimes of fusion components and ensuring credibility of these simulations requires validation over testable domains. Divertors are re…
Showing 1 - 10 of 183 UKAEA Paper Results