A5034358925- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Laser-induced spectroscopy and plasma
- Nuclear Materials and Properties
- Atomic and Molecular Physics
- Meteorological Phenomena and Simulations
- Research Data Management Practices
- Distributed and Parallel Computing Systems
- Computational Fluid Dynamics and Aerodynamics
- Nuclear Physics and Applications
- Anomaly Detection Techniques and Applications
- High-Energy Particle Collisions Research
- Scientific Computing and Data Management
- Fault Detection and Control Systems
- Geophysics and Gravity Measurements
- Nuclear Engineering Thermal-Hydraulics
National Agency for New Technologies, Energy and Sustainable Economic Development
2014-2024
Culham Centre for Fusion Energy
2023-2024
Culham Science Centre
2011-2023
United Kingdom Atomic Energy Authority
2022
Oak Ridge National Laboratory
2022
Royal Military Academy
2020
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati
2016
Aalto University
2013
University of Basilicata
2011
Institute of Plasma Physics and Laser Microfusion
2011
Heat and particle loads on the plasma facing components are among most challenging issues to be solved for a reactor design. Alternative magnetic configurations may enable tokamak operation with lower peak heat load than standard single null (SN) divertor. This papers reports creation control of one such alternatives: two-null nearby divertor configuration. An important element this study is that was produced large superconducting as an experimental advanced tokamak. A preliminary experiment...
Modern epidemiological analyses to understand and combat the spread of disease depend critically on access to, use of, data. Rapidly evolving data, such as data streams changing during a outbreak, are particularly challenging. Data management is further complicated by being imprecisely identified when used. Public trust in policy decisions resulting from easily damaged often low, with cynicism arising where claims ‘following science’ made without accompanying evidence. Tracing provenance...
Abstract We present an overview of results from a series L–H transition experiments undertaken at JET since the installation ITER-like-wall (JET-ILW), with beryllium wall tiles and tungsten divertor. Tritium, helium deuterium plasmas have been investigated. Initial in tritium show ohmic transitions low density power threshold for ( P LH ) is lower than ones densities, while we still lack contrasted data to provide scaling high densities. In there notable shift which minimum <?CDATA...
Abstract The recent deuterium–tritium campaign in JET-ILW (DTE2) has provided a unique opportunity to study the isotope dependence of L-H power threshold an ITER-like wall environment (Be and W divertor). Here we present results from dedicated transition experiments at JET-ILW, documenting tritium plasmas, comparing them with matching deuterium hydrogen datasets. From earlier it is known that as plasma isotopic composition changes deuterium, through varying deuterium/hydrogen concentrations,...
Abstract This paper reports the first experiment carried out in deuterium–tritium addressing integration of a radiative divertor for heat-load control with good confinement. Neon seeding was time D–T plasma as part second campaign JET its Be/W wall environment. The technical difficulties linked to re-ionisation heat load are reported T and D–T. compares impact neon on plasmas their D counterpart detachment, localisation radiation, scrape-off profiles, pedestal structure, edge localised modes global
Since the 2012 IAEA-FEC Conference, FTU operations have been largely devoted to runaway electrons generation and control, exploitation of 140 GHz electron cyclotron (EC) system liquid metal limiter elements. Experiments on shown that measured threshold electric field for their is larger than predicted by collisional theory can be justified considering synchrotron radiation losses. A new control algorithm was developed tested in presence a current plateau, allowing minimize interactions with...
As in many of today's tokamaks, plasma start-up ITER will be performed limiter configuration on either the inner or outer midplane first wall (FW). The massive, beryllium armored FW panels are toroidally shaped to protect panel-to-panel misalignments, increasing deposited power flux density compared with a purely cylindrical surface. chosen shaping should thus optimized for given radial profile parallel heat flux, scrape-off layer (SOL) ensure optimal spreading. For plasmas limited this is...
The electron temperature and density pedestals tend to vary in their relative radial positions, as observed DIII-D (Beurskens et al 2011 Phys. Plasmas 18 056120) ASDEX Upgrade (Dunne 2017 Plasma Control. Fusion 59 14017). This so-called shift has an impact on the pedestal magnetohydrodynamic (MHD) stability hence height (Osborne 2015 Nucl. 55 063018). present work studies effect of JET ITER-like wall (JET-ILW) baseline low triangularity (δ) unseeded plasmas, similar JET-C discharges. As...
Abstract A reduction of the pedestal pressure with increasing separatrix density over ( n e sep / ped ) has been observed in JET. The physics behind this correlation is investigated. due to two distinct mechanisms. increase till ≈0.4 shifts radially outwards, decreasing peeling-balloning stability and reducing height. effect position saturates above ≈ 0.4. For higher values, ascribed increased turbulent transport and, likely, resistive MHD effects. reduces ∇ /n , η transport. This gradient...
Abstract The required heating power, <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>P</mml:mi> <mml:mi>LH</mml:mi> </mml:mrow> </mml:msub> </mml:math> , to access the high confinement regime (H-mode) in tritium containing plasmas is investigated JET with ITER-like wall at a toroidal magnetic field of <mml:mi>B</mml:mi> <mml:mi>t</mml:mi> <mml:mo>=</mml:mo> <mml:mn>1.8</mml:mn> T and plasma current <mml:mi>I</mml:mi>...
Measurements of the ion currents to and plasma conditions at low-field side (LFS) divertor target plate in low-confinement mode plasmas JET ITER-like wall materials configuration show that core density required detach LFS is independent hydrogenic species protium, deuterium tritium, a 40 %/60 % deuterium–tritium mixture. This observation applies with strike line connected horizontal part chosen because its superior diagnostic coverage. The finding operational status cryogenic pump. electron...
Abstract JET, the world’s largest operating tokamak with unique Be/W wall and tritium handling capability, completed a Deuterium-Tritium (D-T) campaign in 2021 (Maggi et al 29th Fusion Energy Conf. ) following decade of preparatory experiments, dedicated enhancements, technical rehearsals training (Horton 2016 Eng. Des. 109–111 925). Operation raises significant technical, safety scientific challenges not encountered standard protium or deuterium operation. This contribution describes...
We present a study of the power threshold for L–H transitions (PLH) in almost pure helium plasmas, obtained recent experiments at JET with an ITER-like wall (Be and W divertor). The most notable new result is that density which PLH minimum, , considerably higher than deuterium hydrogen plasmas. discuss possible implications ITER its pre-fusion operating phase.
Abstract Unusually high power loads on the beryllium limiter caused by neutral beam re-ionisation, and much cooler divertor target surfaces were observed during recent JET tokamak tritium campaign. As both phenomena are driven scrape-off layer (SOL) physics, SOL features of 72 H-mode discharges their deuterium references have been studied. The majority (70) had exponentially decaying profiles. plasmas to increased separatrix density collisionality compared references. This is associated with...
Abstract Since the 2016 IAEA Fusion Energy Conference, FTU operations have been mainly devoted to experiments on runaway electrons and investigations into a tin liquid limiter; other involved studies of elongated plasmas dust. The tearing mode onset in high density regime has studied by means linear resistive code MARS, highly collisional regimes investigated. New diagnostics, such as electron imaging spectroscopy system for in-flight triple Cherenkov probe measurement escaping electrons,...
In this contribution a benchmark of the 2D edge codes TECXY and EDGE2D-EIRENE is presented. A conventional DEMO scenario considered by assuming simplified geometry, with target plates perpendicular to separatrix, pure Deuterium plasma. Despite different models adopted in two codes, mainly related description neutral dynamics boundary conditions, results show good match both terms power load profiles on outer predicted trends for global quantities. scan density diffusion coefficients...