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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(25)152023
Reduced plasma models play a pivotal role in swiftly interpreting experiments, exploring different reactor design points, and providing consistency checks for high-fidelity simulations. This presentation focuses on reduced models for plasma detachment onset and transient reattachment timescales, assessing their validity across ASDEX Upgrade, JET…
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UKAEA-CCFE-CP(25)102023
Fusion power is a critical part of the future energy landscape yet is all too often depicted with the focus on the fusion reaction itself with little attention on supporting systems. In practice of course a real power plant will have the tokamak surrounded by a plethora of ancillaries: the fuel cycle, cooling systems, diagnostics, radiation managem…
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UKAEA-CCFE-PR(25)2882023
Dedicated experiments were performed in JET DTE2 plasmas for obtaining α-particle bump-on-tail (BOT) distribution aiming at exciting Alfvén Eigenmodes (AEs) in baseline tokamak plasma scenario with safety factor q(0)~1. NBI-only heating with modulated power was used so that fusion-born α-particles were the only ions present in the MeV energy ran…
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UKAEA-CCFE-CP(25)042023
2021 has culminated with the completion of the JET-ILW DTE2 experimental campaign. This contribution summarizes Ion Cyclotron Resonance Heating (ICRH) operations from system and physics point of view. Improvements to the (ICRH) system, to operation procedures and to real time RF power control were implemented to address specific constraints from…
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UKAEA-CCFE-PR(25)2682023
In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure no production of neutrons from fusion reactions. With the expected higher L-H power threshold of hy…
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UKAEA-STEP-PR(25)272023
Electron Bernstein current drive (EBCD) systems are sensitive to plasma and launch conditions, and therefore require large parametric scans to optimise their design. One particular bottleneck in the simulation workflow is quasilinear modelling of current drive efficiency. Linear adjoint models are an attractive alternative, offering a ∼103× spee…
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UKAEA-CCFE-CP(24)142023
Accurate quantification of the power loss channels and overall power balance of the plasma is essential for the safe operation of current and future fusion devices. The relative magnitudes of core radiation, SOL radiation and divertor target heat loading are determining factors in both PFC design and plasma scenario design in the successful real…
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