-
UKAEA-CCFE-PR(22)422022
Manufacturing austenite stainless steels (ASSs) using additive manufacturing (AM) is of great interest for cryogenic applications. Here, the mechanical and microstructural responses of a 316L ASS built by laser powder-bed-fusion (L-PBF) were revealed by performing in situ neutron diffraction tensile tests at the low-temperature range (from 373 to 1…
-
UKAEA-CCFE-CP(22)082022
The charged particle heat load assessed for the DEMO Single Module Segment First Wall (FW) during current off-normal plasma scenarios underlines that protection is needed for avoiding/reducing damage to the Breeding Blanket FW due to the deposition of a huge amount of energy in a small timescale. Within the “Key Design Integration Issue 1”, an…
-
UKAEA-CCFE-CP(22)072022
Neutron spectrum unfolding using activation foils is currently the primary technique planned for measuring the neutron energy spectrum at the first wall of power-generating fusion reactors. Room for improvement in the effectiveness of current foil selection was identified, and a program produced to select foils procedurally in order to maximise the…
-
UKAEA-CCFE-CP(22)062022
We present new two applications, AURORA and Achlys, developed using the MOOSE framework for finite element analysis, intended to facilitate engineering analysis for fusion reactors. Respectively these couple neutronics and tritium transport to native MOOSE physics modules including heat conduction and tensor mechanics. We outline steps taken to pe…
-
UKAEA-CCFE-PR(22)412022
-
UKAEA-CCFE-PR(22)402022
In this paper, we review the confinement and transport properties observed and predicted in low aspect ratio tokamaks, or spherical tokamaks (STs), which can depart significantly from those observed at higher aspect ratio. In particular, thermal energy confinement scalings show a strong, near linear dependence of energy confinement time on toroidal…
-
UKAEA-CCFE-PR(22)502022
Fusion power plant designs based on magnetic confinement, such as the tokamak design, offer a promising route to sustainable fusion power but require robust exhaust solutions capable of tolerating intense heat and particle fluxes from the plasma to material surfaces. Turbulent plasma transport in the divertor volume – the region where the plasma-…
-
UKAEA-CCFE-PR(22)382022
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The performance of these steels will deteriorate during service due to neutron damage and transmutation-induced gases, such as helium/hydrogen, at elevated operating tempera…
-
UKAEA-CCFE-PR(22)372022
Neutron flux measurements are important in fusion devices for both safety requirements and physics studies. A newsystem has been built for the Mega Amp Spherical Tokamak Upgrade (MAST Upgrade) that provides neutron count,DC and Campbell mode measurements for a 1μsperiod at 1 MHz. The acquisition system uses a Red Pitaya board tosample current from…
-
UKAEA-CCFE-PR(22)392022
In the absence of official standards and guidelines for nuclear fusion plants, fusion designers adopted, as far as possible, well-established standards for fission-based nuclear power plants (NPPs). This often implies interpretation and/or extrapolation, due to differences in structures, systems and components, materials, safety mitigation systems,…
Showing 611 - 620 of 2527 UKAEA Paper Results