-
UKAEA-STEP-PR(25)262024
STEP (Spherical Tokamak for Energy Production) is the UK’s reactor design programme aiming to demonstrate net electrical output from a spherical tokamak. STEP requires completely non-inductive current drive for the flat-top and the majority of the ramp-up/down phases. The majority of the current (~80%) is generated by a high bootstrap fraction…
-
UKAEA-CCFE-PR(24)2282024
This work presents a system upgrade of the High Resolution Thomson Scattering (HRTS) diagnostic on JET that allows it to measure low temperature (1 to 500 eV) plasma pre- and post-Thermal quench (TQ), which would help to further the understanding of the physics in SPI experiments. The upgrade was done by connecting optic fibres from the original…
-
UKAEA-CCFE-PR(24)2572023
Measuring temperatures between 100 and 150 million degrees, expected to be achieved in future fusion reactors, is a great challenge. Existing methods deliver ion temperature results with a delay from 5-10 minutes to several days after taking the measurements. A promising novel approach to real-time monitoring of deuterium-tritium plasma temperature…
-
UKAEA-CCFE-PR(24)2512023
The injection of energetic neutral particles into the plasma of magnetic confinement fusion reactors is a widely-accepted method for heating such plasmas; various types of neutral beam are also used for diagnostic purposes. Accurate atomic data are required to properly model beam penetration into the plasma and to interpret photoemission spectra…
-
UKAEA-CCFE-PR(23)1592023
Fusion power output from spherical tokamaks would benefit from increased confined plasma density, but there exists a limit on the density before confinement is lost and the plasma current is disrupted. This density limit has long been characterized by a simple, global Greenwald limit proportional to the plasma current and inversely proportional …
-
UKAEA-CCFE-PR(23)1352023
Nuclear data, describing neutron reaction probabilities (cross sections) and decay behaviour, are critical to the design and operation of fusion experiments and future fusion power plants. Equally vital, are the inventory codes that use the data to predict neutron-induced activation and transmutation of materials, which will define the radiologica…
-
UKAEA-CCFE-CP(23)422022
A tungsten Langmuir probe exposed in the JET divertor during the ITER-like wall campaigns (ILW) has been studied to evaluate changes in mechanical properties and microstructure. The tip of the probe that was exposed to plasma was cross-sectioned and polished for post mortem analysis. Analysis involved a comparison with a non-exposed probe to de…
-
UKAEA-STEP-PR(23)062022
To support the design of fusion reactors for energy production, there is an urgent need to develop highly-scalable multi-physics software tools capable of modelling critical tokamak components as a single cohesive whole. Although some loosely-coupled physics tools do exist, these lack fidelity and will fundamentally fail to capture any closed-lo…
-
UKAEA-CCFE-PR(22)182022
A new method for the calculation of Shutdown Dose Rates (SDDR) has been developed, the Novel-1-Step (N1S) method. The new method retains the benefits of only requiring a single radiation transport calculation, as in the use of the direct-1-step (D1S) method, while removing the need for pre-calculations to determine dominant nuclides and time corr…
-
UKAEA-CCFE-PR(21)082021
A survey of the correlation between temperature and density gradient lengths ( and ) has been performed for the near SOL regions in the ASDEX Upgrade tokamak. In common with previous studies, the near SOL temperature and density gradient length ratio, , is found to be close to unity across a wide range of plasmas. However, it is found that it is po…
Showing 1 - 10 of 70 UKAEA Paper Results