14 MeV calibration of JET neutron detectors-phase 2: in-vessel calibration

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The Fast Discharge Units (FDUs) of the Superconducting (SC) Toroidal Field (TF) coils in the European demonstration fusion power plant DEMO warrant the machine integrity over its full lifetime against severe failure events, such as SC coil quenches or any ...

Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in Tokamak & agrave; Configuration Variable (TCV) single-null, L-mode discharges. Scans of nitrogen seeding rate are con ...

Plasma shape control is a fundamental tool for effective tokamak operation, allowing improved plasma performance and the pursuit of challenging scientific objectives. In this framework, the Tokamak á Configuration Variable (TCV) of the École Polytechnique ...

Conducting neutron scattering experiments in the presence of high pulsed magnetic fields, namely above 40 T, provides valuable information about the magnetic structures of materials. However, these experiments are challenging and time-consuming because the ...

JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET’s 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-dept ...

MAST-U is equipped with on-axis and off-axis neutral beam injectors (NBI), and these external sources of super-Alfv & eacute;nic deuterium fast-ions provide opportunities for studying a wide range of phenomena relevant to the physics of alpha-particles in ...

Metasurfaces provide an ideal platform for optical sensing because they produce strong light-field confinement and enhancement over extended regions that allow us to identify deep-subwavelength layers of organic and inorganic molecules. However, the requir ...

DT operations at JET gave a unique and invaluable opportunity to design, develop and test real -time controllers that will be applied in future burning plasma devices, as ITER and SPARC. Among them, the dud detector [L. Piron et al. 2019 Fusion Eng. Design ...

The plasma density is a crucial parameter of tokamak discharge as it impacts the fusion power, stability limits, influences detachment onset and impurities transport. The electron density profile shaping affects the deposition location of the external heat ...

The design point that had been chosen for EU DEMO in 2016 is reviewed here and a modification is proposed with a lower aspect ratio. Previously the same aspect ratio, A, was chosen for EU DEMO as in major tokamak experiments including ITER (A = 3.1), and, ...

We analyze a measure for the degree of chaos in the magnetic fields of magnetic confinement fusion reactors by calculating the lobe fluxes of turnstiles - a method developed for characterizing transport into and out of resonance zones in Hamiltonian dynami ...

Combined high-fusion performance and long-pulse operation is one of the key integration challenges for fusion energy development in magnetic devices. Addressing these challenges requires an integrated vision of physics and engineering aspects with the purp ...

In tokamaks, rotating magneto-hydro-dynamic modes frequently decelerate as their amplitude increases. Once a critical threshold in amplitude is reached, these modes stop rotating into a specific toroidal and poloidal position and are commonly named Locked ...

In order to cope with the decarbonization challenge faced by many countries, fusion is one of the few alternatives to fossil fuels for the production of electricity. Two devices invented in the middle of the previous century have emerged as the most promis ...

The quasi-continuous exhaust (QCE) regime is a type-I ELM-free high confinement regime obtained at high plasma shaping and high separatrix density. A comparison with various ELM-free regimes in the literature is presented together with potential physics mo ...

Noise measurements in light water reactor systems aid in generating validation data for integral point kinetic parameter predictions and generating monitoring parameters for reactor safety and safeguards. The CROCUS zero-power reactor has been used to supp ...

In preparation for error field (EF) identification experiments in ITER, a series of experiments have been conducted at JET to test the portability of the non-disruptive compass scan, a method originally designed and tested in DIII-D (Paz-Soldan et al 2022 ...

Plasma turbulence plays a fundamental role in determining the performances of magnetic confinement fusion devices, such as tokamaks. Advances in computer science, combined with the development of efficient physical models, have significantly improved our u ...

The compact design of microreactors can potentially lead to a strong interdependence between neutronics and thermo-mechanics, making the development of coupling methodologies essential to quantify the importance of such effects. This study introduces a hig ...

In magnetic fusion devices, error field (EF) sources, spurious magnetic field perturbations, need to be identified and corrected for safe and stable (disruption-free) tokamak operation. Within Work Package Tokamak Exploitation RT04, a series of studies hav ...

14 MeV calibration of JET neutron detectors-phase 2: in-vessel calibration

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DEMO toroidal field coil fast discharge unit integration studies

Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments

Design and implementation of a model-based hierarchical architecture for plasma shape control in the TCV tokamak

High brightness neutron source optimized for very high pulsed magnetic field experiments

Overview of the third JET deuterium-tritium campaign

Overview of fast particle experiments in the first MAST Upgrade experimental campaigns

Plasmonic biosensor enabled by resonant quantum tunnelling

Innovative dud detection based on JET DT experience

Real-time density profile simulations on ASDEX Upgrade and the impact of the edge boundary condition

Re-design of EU DEMO with a low aspect ratio

Turnstile flux as a measure for chaotic transport in magnetic confinement fusion devices

Long plasma duration operation analyses with an international multi-machine (tokamaks and stellarators) database

Machine learning methods for locked-mode predictions in MAST-U plasmas

Global fluid simulations of plasma turbulence in stellarators

The quasi-continuous exhaust regime in ASDEX Upgrade and JET

Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators

Lessons Learned Executing the Non-disruptive Compass Scan Method at Jet Towards Error Field Identification Experiments in Iter

Nonlinear simulation of plasma turbulence using a gyrokinetic moment-based approach

Cell-Wise Temperature and Deformation Reactivity Feedback Modeling in Heat Pipe-Cooled Microreactors

Error field detection and correction studies towards ITER operation