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UKAEA-STEP-PR(25)292025
Systems models and associated cost analyses are widely used within the fusion community to analyse tokamak designs, from prototype and demonstrator machines to potential commercial fusion power plants. To ensure the design programmes of fusion prototype/demonstrator power plants deliver a cost optimised design (within existing uncertainty limita…
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2025
AC losses in the high temperature superconducting (HTS) toroidal field (TF) magnets of the STEP tokamak are analysed, focusing on the transient electromagnetic response of the centre column to the charging and discharging of the central solenoid (CS) and poloidal field (PF) magnets during a plasma initiation scenario. An innovative H-H…
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UKAEA-CCFE-PR(25)2952025
The DEMO fusion reactor Divertor design group within the EUROfusion consortium use RCC-MRx as the main analysis code for the Divertor’s structural integrity assessment. Analysis has been carried out within the same group using an in-house developed Finite Element Analysis post processing script which follows the Design by Elastic Analysis rule…
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UKAEA-STEP-PR(24)232024
Electron Bernstein waves (EBWs) are theorised to efficiently drive current in spherical tokamak power plants, e.g. Spherical Tokamak for Energy Production (STEP). At high temperatures (Te ≳4keV), relativistic effects can significantly impact wave propagation. This work presents relativistic calculations of EBW wave propagation, damping, and curre…
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UKAEA-CCFE-PR(26)4562024
A Gas Electron Multiplier (GEM) based detector was exploited for the first time on the MASTU tokamak during the 2023 campaign to investigate Soft X-Ray (SXR) radiation (1-20keV) emitted from the plasma. SXR radiation carries essential information on electron temperature and density, impurity presence, and Magneto-hydrodynamic (MHD) activities, m…
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UKAEA-CCFE-PR(26)4552024
The linear MHD peeling-ballooning stability analysis on the ELM-free phase of MAST Upgrade H-mode plasma is presented. In contrast to other similar discharges, #47018 is found to have significantly higher and wider pedestal during an ELM-free H-mode phase that lasts for approximately 80ms, which is made possible by the reduced core MHD mode acti…
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UKAEA-CCFE-PR(26)4512024
An understanding of the behaviour of the D or He fuel used in tokamak discharges is essential in analyses such as modelling edge and divertor transport and the erosion of the vessel walls. However, poor agreement is found between measurements made on the JET tokamak and collisional-radiative models used …
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UKAEA-CCFE-CP(26)452024
A real-time plasma magnetic equilibrium controller has been developed to aid in the precise control of advanced configurations such as double-null, super-X, X-point target and X-divertor for the first time on the MAST Upgrade (MAST-U) tokamak. Successful real-time magnetic equilibrium control of different plasma shape control variables during th…
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UKAEA-CCFE-CP(26)342024
The MAST-U spherical tokamak (ST) is equipped with on-axis and off-axis neutral beam injectors (NBI), external sources of super-Alfvénic fast ions that provide opportunities for studying a wide range of phenomena relevant to the physics of alpha-particles in future burning plasma devices such as STEP or ITER. High performance of MAST-U plasmas rel…
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UKAEA-CCFE-PR(25)4042024
JET is the only tokamak capable of Deuterium-Tritium (D-T) operations. The first D-T operations were in the 1990s and again in 2004. In 2020/2021 JET operated a much larger D-T campaign aimed at sustained high fusion power requiring a much higher tritium throughput. This paper presents an overview of the recent Tritium Injections into the JET To…
Showing 11 - 20 of 530 UKAEA Paper Results