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UKAEA-CCFE-PR(24)2322024
The JET-ILW pure Tritium and Deuterium-Tritium (DTE2) experimental campaigns took place in 2021-2022. Tritium (T) and Deuterium-Tritium (D-T) operations present challenges not encountered in present day tokamaks [1]. This contribution focuses on Ion Cyclotron Resonance Heating (ICRH) operations in tritium and deuterium-tritium plasmas, starting …
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UKAEA-STEP-PR(24)152024
The Spherical Tokamak for Energy Production(STEP) environment will include magnetic, thermal, mechanical and environmental loads far greater than those seen in the Joint European Torus campaigns of the past decade or currently contemplated for ITER. Greater still are the neutron peak dose rates of 10−6 displacements per atom, per second, which in…
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UKAEA-STEP-PR(24)102024
Fusion is inherently safer than fission due to the absence of nuclear chain reactions. However, operating fusion power plants will not be risk free. There will still be numerous hazards that will need careful management in order to safely build, operate and ultimately decommission a fusion power plant. Ensuring a robust safety demonstration that…
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UKAEA-STEP-PR(24)092024
The STEP Prototype Powerplant (SPP) will be a first of a kind powerplant – its prime objective is to export electrical power, to the grid, above 100MWe. As part of a wider issue, addressing the STEP concept design, this paper seeks to explore how electrical power will be generated from a Spherical Tokamak heat source. Accordingly, the followin…
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UKAEA-CCFE-PR(24)2112024
REBCO coated conductor tapes are a highly attractive option for magnet materials in future tokamak fusion power plants. However, the threat of intense neutron and gamma radiation, plus AC loss power dissipation during magnet coil ramping, raises concerns around REBCO magnet coil lifetimes. Irradiation-induced flux creep, or AC loss, has been ide…
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UKAEA-STEP-PR(24)022024
Being a novel technology, estimating costs for fusion power plants comes with large uncertainties. Cost uncertainties in prototypes arise from various sources and reduce with programme maturity (including the selection of a site), technical and design maturity, maturity of the commercial strategy (e.g., make vs. buy decisions, partnering decisions)…
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UKAEA-CCFE-PR(24)032024
To design a safe termination scenario for a burning ITER plasma is a challenge that requires extensive core plasma and divertor modelling. The presented work consists of coupled core/edge/SOL/divertor simulations, performed with the JINTRAC code, studying the Q=10 flat-top phase and exit phase of the ITER 15MA/5.3T DT scenario. The modelling uti…
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UKAEA-CCFE-CP(26)422023
Spherical tokamaks show great potential in being the basis for a compact fusion power plant. With a reduced aspect ratio and the benefit of increased plasma performance, spherical tokamaks provide a pathway for tokamak electricity production with reduced capital costs compared to conventional aspect ratio tokamak power plant designs. The…
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UKAEA-CCFE-CP(26)402023
A key objective of fusion research is to develop pathways to integrate good confinement in the core and pedestal with strong dissipation of power and particles in the divertor through a combination of experimental demonstration and modelling. The MAST Upgrade spherical tokamak has unique capabilities to find solutions to this integration challeng…
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UKAEA-CCFE-PR(25)3912023
Accurate computation of power deposition is expected to be critical for the successful design of plasma facing components (PFCs) in reactor-scale magnetic confinement devices. The work provides analysis and model computations to help explain the high levels of accuracy obtainable using relatively coarse meshing of PFCs to treat cases with shar…
Showing 31 - 40 of 500 UKAEA Paper Results