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UKAEA-CCFE-CP(23)542022
Several Ion Cyclotron Resonance Heating (ICRH) schemes in DT plasma have been considered for the ITER reactor [1]. Most of these heating schemes are minority heating at fundamental frequency. In DT plasma, both reactants can also absorb RF power as majorities at fundamental n=1 or harmonic n=2 frequency. Understanding benefits of directly heatin…
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UKAEA-STEP-CP(23)102022
The work presented in this paper is an integrated time-dependent model, describing the power demands of the major tokamak components (magnets, cryogenics, heating and current drive, etc.), as well as the power generated. The physics are implemented in OpenModelica and make use of a Python API (Application Programming Interface) to collect inputs, r…
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UKAEA-CCFE-CP(23)532022
The ITER Heating Neutral Beam (HNB) source prototype SPIDER (Source for the Production of Ions of Deuterium Extracted from a Radio frequency plasma), hosted at the Neutral Beam Test Facility (NBTF) in Padova, Italy, has recently started operating with evaporated caesium in the source. This moves the primary H- production mechanism from volume to…
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UKAEA-CCFE-CP(23)522022
An investigation was conducted into minimising effective dose to members of the public in the unlikely event of an accident by optimising design parameters and site locations of future fusion power plants. This is part of our defence in depth approach for tritium safety that also includes significant work on the prevention of accidents. Calculat…
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UKAEA-CCFE-CP(23)512022
The EU DEMO power plant is the final stage of the EUROfusion Fusion Technology Programme’s route to commercially viable electricity supply [1]. The selection of apposite technologies for DEMO power plant sub-systems is essential. The breeding blanket, responsible for absorption of nuclear energy, tritium fuel production and a substantial proporti…
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UKAEA-STEP-PR(23)072022
To mitigate the issue of plasma exhaust in reactor scale tight aspect ratio tokamaks such as STEP (Spherical Tokamak for Energy Production), a double-null (DN) configuration is thought to be advantageous over a single-null (SN) configuration. However, practical control of the plasma vertical stability will likely lead to an oscillation around th…
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UKAEA-CCFE-CP(23)432022
MAST Upgrade (MAST-U) is a new low aspect ratio device (R/a = 0.85/0.65 ~ 1.3) based on the MAST tokamak that started plasma operations in October 2020. It has substantial new capabilities compared with the original MAST device, with 19 new poloidal field coils (14 of which are within the vacuum vessel) and new, closed, up-down symmetric diverto…
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UKAEA-STEP-CP(23)072022
With steady progress on ITER project and the design of DEMO, the international community is now entering an era in which fusion power on the grid could become a reality within the next 20 – 30 years. In this environment the UK has started the ambitious Spherical Tokamak for Energy Production (STEP) programme, aiming to develop a compact protot…
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UKAEA-STEP-CP(23)042022
The UK has launched a programme to build a prototype fusion power plant, the Spherical Tokamak for Energy Production (STEP), by 2040. It is intended that the STEP prototype will generate fusion power of the order of 1 GW and net electrical power of the order of 100 MW. Plasma scenarios that could be compatible with these design requirements and wit…
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UKAEA-CCFE-PR(23)082022
The role of ion-molecule elastic collisions (specifically D+−D2 collisions) in strongly detached divertor conditions has been studied in the MAST-U Super-X configuration using SOLPS-ITER. Two strongly detached steady state solutions, one obtained through a main-ion (D2) fuelling scan and the other through an impurity (N) seeding scan at fixed …
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