A5034498633- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Nuclear physics research studies
- Atomic and Molecular Physics
- Solar and Space Plasma Dynamics
- Plasma Diagnostics and Applications
- Atomic and Subatomic Physics Research
- Particle Detector Development and Performance
- High voltage insulation and dielectric phenomena
- Anomaly Detection Techniques and Applications
- Radiation Therapy and Dosimetry
- Advanced Frequency and Time Standards
- High-Energy Particle Collisions Research
- Astro and Planetary Science
- Muon and positron interactions and applications
- Ion-surface interactions and analysis
- Advancements in Photolithography Techniques
- Nuclear Materials and Properties
- Statistical Methods and Inference
Aalto University
2016-2025
CEA Cadarache
2024
Tokamak Energy (United Kingdom)
2021-2024
Barcelona Supercomputing Center
2020
VTT Technical Research Centre of Finland
2017-2020
Universitat Politècnica de Catalunya
2020
Royal Military Academy
2020
The SPARC tokamak is a critical next step towards commercial fusion energy. designed as high-field ( $B_0 = 12.2$ T), compact $R_0 1.85$ m, $a 0.57$ m), superconducting, D-T with the goal of producing gain $Q>2$ from magnetically confined plasma for first time. Currently under design, will continue path Alcator series tokamaks, utilizing new magnets based on rare earth barium copper oxide high-temperature superconductors to achieve high performance in device. achievable conservative...
For several reasons the challenge to keep loads first wall within engineering limits is substantially higher in DEMO compared ITER. Therefore pre-conceptual design development for that currently ongoing Europe needs be based on load estimates are derived employing most recent plasma edge physics knowledge.
Abstract Ion temperatures of over 100 million degrees Kelvin (8.6 keV) have been produced in the ST40 compact high-field spherical tokamak (ST). excess 5 keV not previously reached any ST and only obtained much larger devices with substantially more plasma heating power. The corresponding fusion triple product is calculated to be <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>n</mml:mi> <mml:mi>i</mml:mi> <mml:mn>0</mml:mn>...
This paper summarizes the physical principles behind novel three-ion scenarios using radio frequency waves in ion cyclotron range of frequencies (ICRF). We discuss how to transform mode conversion electron heating into a new flexible ICRF technique for and fast-ion generation multi-ion species plasmas. The theoretical section provides practical recipes selecting plasma composition realize scenarios, including two equivalent possibilities choice resonant absorbers that have been identified....
Abstract ST40 is a compact, high-field ( <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>B</mml:mi> <mml:mi mathvariant="normal">T</mml:mi> <mml:mn>0</mml:mn> </mml:mrow> </mml:msub> <mml:mtext>⩽</mml:mtext> <mml:mn>2.1</mml:mn> <mml:mstyle scriptlevel="0"/> <mml:mtext>T</mml:mtext> </mml:math> ) spherical tokamak (ST) with mission to expand the physics and technology basis for ST route commercial fusion. The research programme covers...
The objectives of the nuclear fusion power plant DEMO, to be built after ITER experimental reactor, are usually understood lie somewhere between those and a 'first kind' commercial plant. Hence, in DEMO issues related efficiency RAMI (reliability, availability, maintainability inspectability) among most important drivers for design, as cost electricity produced by this will strongly depend on these aspects. In framework EUROfusion Work Package Heating Current Drive within Power Plant Physics...
Dedicated experiments to generate energetic D ions and fusion-born alpha particles were performed at the Joint European Torus (JET) with ITER-like wall (ILW). Using 3-ion radio frequency (RF) heating scenario, deuterium from neutral beam injection (NBI) accelerated in core of mixed plasmas higher energies ion cyclotron resonance (ICRF) waves, turn leading a core-localized source particles. The fast-ion distribution RF-accelerated D-NBI was controlled by varying ICRF NBI power ( 4–6 MW, 3–20...
Dedicated experiments were conducted in mixed H-D plasmas JET to demonstrate the efficiency of 3-ion ICRF scheme for plasma heating, relying on injected fast NBI ions as resonant ion species.Strong core localization RF power deposition close vicinity ion-ion hybrid layer was achieved, resulting an efficient generation energetic D ions, strong enhancement neutron rate and observation Alfvénic modes.A consistent physical picture that emerged from a range fast-ion measurements at JET, including...
Abstract Mitigating edge localized modes (ELMs) with resonant magnetic perturbations (RMPs) can increase energetic particle losses and resulting wall loads, which have previously been studied in the vacuum approximation. This paper presents recent results of fusion alpha NBI ion ITER baseline scenario modelled Monte Carlo orbit following code ASCOT a realistic field including effect plasma response. The response was found to reduce but losses, up 4.2% injected power being lost. Additionally,...
The isotope dependence of plasma transport will have a significant impact on the performance future D-T experiments in JET and ITER eventually fusion gain economics reactors. In preparation for operation JET, dedicated comprehensive analyses were performed H, D H-D mixed plasmas. analysis data has demonstrated an unexpectedly strong favourable global confinement energy, momentum particles ELMy H-mode plasmas atomic mass main ion species, energy time scaling as ${\tau _E}\sim {A^{0.5}}$...
Abstract A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main chamber wall and tungsten divertor, to reduce plasma deuterium concentration less than 1% preparation for operation tritium. This also a key activity regard refining clean-up strategy be implemented at end 2nd DT campaign JET (DTE2) assess tools that are envisaged mitigate tritium inventory build-up ITER. The began 4 days baking 320 °C, followed by further which Ion Cyclotron Wall...
We present a novel implementation of Monte Carlo particle-following code for solving the distribution function minority species in fusion plasmas, called ASCOT5, and verify it using theoretical results neoclassical transport. The has been developed from ground up with an OpenMP-MPI hybrid paradigm to take full advantage current next generation many-core CPUs multithreading SIMD operations. Up 6-fold increase performance is demonstrated compared previous version which only utilizes MPI....
Abstract Like most magnetic confined fusion experiments, the ST40 tokamak started off with a small subset of diagnostics and gradually increased diagnostic set to include more complex comprehensive systems. To make each operational phase, forward models various are used developed aid design, provide consistency-checks during commissioning, test analysis methods, build workflows constrain high-level parameters inform interpretation, theory modelling. For new workflows, minimum-viable-products...
JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by Japan Europe, is due to start operation in 2020.Its main missions are support ITER exploitation contribute demonstration fusion reactor machine scenario design.Peculiar properties of JT-60SA its capability produce long-pulse, high-β, highly shaped plasmas.The preparation Research Plan, plasma scenarios, producing physics results not only relevant future experiments, but often constitute...
ASCOT Fusion Source Integrator AFSI, an efficient tool for calculating fusion reaction rates and characterizing the products, based on arbitrary reactant distributions, has been developed is reported in this paper. Calculation of reactor-relevant D–D, D–T D–3He reactions implemented Bosch–Hale cross sections. The can be calculated between particle populations, including Maxwellian thermal particles minority energetic particles. Reaction rate profiles, energy spectra full 4D phase space...
Disruption-generated runaway electrons (RE) present an outstanding issue for ITER. The predictive computational studies of RE generation rely on orbit-averaged computations and, as such, they lack the effects from magnetic field stochasticity. Since stochasticity is naturally in post-disruption plasma, and externally induced stochastization offers a prominent mechanism to mitigate avalanche, we advection–diffusion model that can be used couple orbit-following code tool order capture...
The fusion alpha and beam ion with steady-state power loads in all four main operating scenarios of ITER have been evaluated by the ASCOT code. For this purpose, high-fidelity magnetic backgrounds were reconstructed, taking into account even internal structure ferritic inserts tritium breeding modules (TBM). ions found to be almost perfectly confined scenarios, only so-called hybrid scenario featured reaching 0.5 MW due its more triangular plasma. TBMs not jeopardize confinement, nor cause...
Potential loss of energetic ions including alphas and radio-frequency tail due to classical orbit effects magnetohydrodynamic instabilities (MHD) are central physics issues in the design experimental programme SPARC tokamak. The expected fusion alpha power ripple-induced transport is computed for tokamak by ASCOT SPIRAL orbit-simulation codes, assess surface heating plasma-facing components. We find good agreement between simulation results not only integrated quantities (fraction loss) but...
Using the orbit-following code ASCOT, we have modelled fast ion transport in ITER under influence of ELM control coils (ECCs), toroidal field ripple, and test blanket modules, with emphasis on how plasma response (PR) modifies mechanisms loads divertor. We found that while PR shields by healing broken flux surfaces at periphery, it also opens a new loss channel for marginally trapped particles: causes strong variation poloidal near X-point which leads to de-localisation banana tips...
The orbit-following Monte Carlo code ASCOT interfaced with the radiofrequency library RFOF can simulate heating of ion populations using wave solutions from full-wave solvers such as TORIC. It is applied to fundamental mode cyclotron resonant hydrogen and 2nd harmonic frequency neutral beam injected deuterium in ASDEX Upgrade discharge #33147 validate model against fast loss detector (FILD) measurements. In addition, for FILD signal simulations requiring enhanced resolution or scanning...
Most auxiliary heating methods provide to more than one particle species (electrons, ions, impurities) in a fusion plasma. This can lead substantial temperature differences between species, depending on conditions such as power the different and collisionality, with limited by inter-species thermal equipartition transport. The analysis of steady-state electron-ion impurity-ion balances presented this paper are used for consistency-checking experimental ion electron measurements inferring...
The studies of recent JET experiments in H/D≈0.85/0.15 plasma (2.9T/2MA) which neutron rate was enhanced by applying 2.5MW ICRH using D-(DNBI)-H three-ion scheme are reported. An extensive analysis this novel heating scenario has been carried out means integrated TRANSP/TORIC modelling, and a comprehensive validation the computed Fast Ion Distribution Function (FI DF) with range fast ion diagnostics available at is presented. predicted acceleration D Neutral Beam Injection (NBI) ions beyond...
This paper provides a comprehensive study of neutron calibration methodologies, specifically highlighting the capabilities for n–γ discrimination in diamond and EJ-309, stilbene scintillation detectors. The process detailed this includes pulse height analysis shape discrimination, relying on charge deposition resulting from both γ interactions. Utilizing 60Co 252Cf radiation sources, energy spectra these sources are obtained. characterized detectors were used ST40 experiments allowed...
JETPEAK is a comprehensive stationary-state database and work environment for JET diagnostics data, processed data simulations suitable wide variety of analytical tasks. It enables systematic modelling efficient interpretation synthetic neutron validation fast particle fusion product calculations. We present processing chain connecting the ASCOT orbit following code AFSI source simulator Monte-Carlo codes, providing comparison with measured model validation. The defines reactant distribution...
This paper addresses the confinement of thermonuclear alpha particles and neutral beam injected deuterons in 15 MA Q = 10 inductive scenario presence magnetic perturbation caused by helium cooled pebble bed test blanket module using vacuum approximation. Both flat top phase plasma ramp-up are studied. The transport fast ions is calculated Monte Carlo guiding center orbit-following code ASCOT. A detailed three-dimensional wall, derived from ITER CAD data, used for evaluating ion wall loads....