-
UKAEA-CCFE-CP(20)892020
The EUROfusion Roadmap for fusion research was recently updated and describes a clear set of missions and associated goals on the route to commercial fusion electricity. Beyond ITER, the main target of the programme is the development of DEMO, a fusion technology demonstrator which will produce substantial net electrical output, breed its own fu…
-
UKAEA-CCFE-CP(20)1042018
During the pre-conceptual design phase of fusion devices such as the European demonstration fusion power plant (DEMO), systems codes provide a fast evaluation of optimal design points and highlight high impact areas. However, determining or evaluating a design point at such an early stage comes with uncertainties in many of the design parameters. T…
-
UKAEA-CCFE-CP(20)792018
The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…
-
CLM P7421985
-
UKAEA-CCFE-PR(20)022019
Shear strain profiles along slip bands in a modified Rolls-Royce nickel superalloy (RR1000) were analyzed for tensile sample deformed by 2%. The strain increased with distance away from a grain boundary (GB), with maximum shear strain towards the center of the grain, indicating that dislocation nucleation generally occurred in the grain interior. T…
-
UKAEA-CCFE-CP(19)452019
Spherical Tokamaks offer a number of potential advantages for a future fusion power plant. They have a high ratio of thermal to magnetic field pressure (beta) and strong flows, either of which could result in reduced turbulence. Fewer Toroidal Field (TF) coils and a different geometry offers the potential for new methods of remote maintenance …
-
UKAEA-CCFE-CP(19)442019
MAST has undergone a substantial upgrade [1], featuring among other things several new poloidal field coils mostly distributed around the new closed-throat divertor structure and an enlarged centre column. The considerable changes have required the plasma control software to be substantially re-written. The MAST digital plasma control system […
-
UKAEA-CCFE-CP(19)372019
As conceptual design options for a demonstration fusion power plant (DEMO) are explored it is important to understand the design space for possible non-ITER like design options. The power exhaust is a key design driver for a fusion power plant, and puts strong constraints on the size of the machine. One candidate for a alternative design is a doubl…
-
UKAEA-CCFE-PR(19)752019
The evolution of the JET high performance hybrid scenario, including central accumulation of the tungsten (W) impurity, is reproduced with predictive multi-channel integrated modelling over multiple confinement times using first-principle based models. 8 transport channels are modelled predictively, with self-consistent sources, radiation and magne…
-
UKAEA-CCFE-CP(19)542018
Protecting the divertor in a nuclear fusion power plant is a key criteria for operation. Detailed divertor and scrape-off-layer (SOL) modelling is computationally intensive and unsuitable for a systems code. For the use of such models in systems codes they need to be simplified and made computationally fast, while still capturing the most important…
Showing 11 - 20 of 69 UKAEA Paper Results