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UKAEA-CCFE-PR(26)4172025
Two ferritic Oxide Dispersion Strengthened (ODS) steels Fe-12Cr-YWT and Fe-14Cr-YWT were irradiated in the High Flux Reactor (HFR) up to 3 dpa at a nominal temperature of 600°C. Tensile tests at room and elevated temperatures as well as microstructural investigations using transmission electron microscopy (TEM) and atom probe tomography (APT) were…
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UKAEA-CCFE-CP(25)232025
The feasibility of laser-induced breakdown spectroscopy (LIBS) for measuring fuel retention was demonstrated for the first time in a tokamak operating with tritium using a remotely controlled in situ application in JET. In JET and future fusion reactors such as ITER and DEMO, thick co-deposited layers will be formed at the inner wall during exte…
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UKAEA-CCFE-PR(25)3552025
This study presents results from particle transport modelling for D/T ratio control experiments conducted during the JET DTE3 campaign. TRANSP interpretative and JETTO predictive simulations for D and T densities were performed and their results are discussed. Despite using simplified models based on Bohm-gyroBohm transport, the simulations inco…
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UKAEA-CCFE-PR(25)3372025
Most research reactors (RRs) in Europe are over 60 years old, and there are only limited efforts underway (e.g., PALLAS and JHR projects) to partially replace this aging infrastructure. Continued safe operation (CSO) of these reactors is crucial to sustaining the EU’s leadership in nuclear materials development and qualification for advanced r…
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UKAEA-CCFE-PR(25)3252025
Maintaining an effective double-null configuration is expected to be challenging in reactor-scale tokamak devices. As divertor power-sharing is closely linked to the magnetic topology, even small variations can lead to fast power sharing fluctuations which exacerbate the already daunting exhaust challenge. While the static aspects of doubl…
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UKAEA-CCFE-PR(25)3202024
The development of a high current baseline scenario (I_p = 3.5MA, q95 ~3.0, beta_N < 2) in deuterium (D), tritium (T) and deuterium-tritium (D-T) for high DT fusion performance at JET with Be/W wall is described. We show that a suitable scenario capable of delivering up to 10 MW of fusion power, depending on the auxiliary heating power avail…
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UKAEA-CCFE-PR(25)2672024
The first generation of nuclear fusion reactors is expected to operate using a mixture of deuterium(D) and tritium(T) fuel. Controlling the D:T ratio is a promising option to control the fusion burn rate. The Joint European Torus (JET), as the only operational tokamak which can use tritium, is uniquely placed to test th…
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UKAEA-STEP-PR(24)222024
The architecture of STEP has been developed to enable a hybrid maintenance approach, using ports in the vacuum vesselor a limited list of tasks that must be performed shortly after shutdown, and larger openings to simplify and speed-up major refits. Robotic handling systems in zero-human entry facilities will prevent workers from being exposed t…
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UKAEA-CCFE-PR(24)2612024
The fusion reaction between deuterium and tritium, D(T,n)4He is the main source of energy in future thermonuclear reactors. Alpha-particles (4He-ions) born with an average energy of 3.5MeV transferring energy to the thermal plasma during their slowing down, they should provide the self-sustained D-T
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UKAEA-STEP-PR(24)202024
Success of UKs STEP (Spherical Tokamak for Energy Production) programme [1] [2] [3] [4] requires a robust plasma control system. This system has to guide the plasma from initiation to the burning phase, maintain it there, producing the desired fusion power for the desired duration and then terminate the plasma safely. This has to be done in a ch…
Showing 1 - 10 of 76 UKAEA Paper Results