Results 21 to 30 of about 311 (75)

Modelling of 3D fields due to ferritic inserts and test blanket modules in toroidal geometry at ITER [PDF]

open access: yes, 2016
Computations in toroidal geometry are systematically performed for the plasma response to 3D magnetic perturbations produced by ferritic inserts (FIs) and test blanket modules (TBMs) for four ITER plasma scenarios: the 15 MA baseline, the 12.5 MA hybrid,
Akaslompolo, S.   +10 more
core   +2 more sources

Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall [PDF]

open access: yes, 2019
For the past several years, the JET scientific programme (Pamela et al 2007 Fusion Eng. Des.82 590) has been engaged in a multi-campaign effort, including experiments in D, H and T, leading up to 2020 and the first experiments with 50%/50% D–T mixtures ...
Abduallev, Sadrilla   +8 more
core   +2 more sources

Prediction and analysis of JET fusion performance based on reduced first principle transport models [PDF]

open access: yes, 2023
The design of a Tokamak device is carried out initially with a 0D approach aiming at defining the plasma engineering parameters estimated with the help of empirical scaling laws, and the technological limits of the device components.
ZOTTA, VITO KONRAD
core  

Recent EUROfusion Achievements in Support of Computationally Demanding Multiscale Fusion Physics Simulations and Integrated Modeling [PDF]

open access: yes, 2018
Integrated modeling (IM) of present experiments and future tokamak reactors requires the provision of computational resources and numerical tools capable of simulating multiscale spatial phenomena as well as fast transient events and relatively slow ...
Aniel, T.   +40 more
core   +3 more sources

Simulation of heating and current drive sources for scenarios of the ITER research plan [PDF]

open access: yes, 2021
Predicting the impact of heating and current drive (H&CD) sources is essential to evaluate the performance of ITER plasmas and to subsequently optimise the scenarios for the four stages of the ITER research plan. This should be done in the context of
Hoenen, O.   +9 more
core   +2 more sources

First-principle based multi-channel integrated modelling in support to the design of the Divertor Tokamak Test facility [PDF]

open access: yes, 2021
An intensive integrated modelling work of main scenarios of the new tokamak DTT (Divertor Tokamak Test facility) with the Single Null divertor configuration has been performed using first-principle quasi-linear transport models, in support to the design ...
A. Castaldo   +20 more
core  

Fusion power predictions for β N≈ 1.8 baseline scenario with 50-50 D-T fuel mix and NBI injection in preparation to D-T operations at JET [PDF]

open access: yes, 2022
The fusion performance of ELMy H-mode 50-50 deuterium-tritium (DT) plasmas with 50-50 DT NBI injection and q 95 ≈ 3 and β N ≈ 1.8 (also referred to as medium-β N baseline scenario in the rest of this paper) are predicted with the JINTRAC suite of codes ...
Casson F. J.   +12 more
core   +1 more source

Fast modeling of turbulent transport in fusion plasmas using neural networks [PDF]

open access: yes, 2019
We present an ultrafast neural network (NN) model, QLKNN, which predicts core tokamak transport heat and particle fluxes. QLKNN is a surrogate model based on a database of 300 million flux calculations of the quasilinear gyrokinetic transport model ...
Bourdelle, Clarisse   +9 more
core   +2 more sources

ASCOT: solving the kinetic equation of minority particle species in tokamak plasmas

open access: yes, 2013
A comprehensive description of methods, suitable for solving the kinetic equation for fast ions and impurity species in tokamak plasmas using Monte Carlo approach, is presented.
Asunta, Otto   +7 more
core   +1 more source

Predictive simulations of deuterium fuelling in DTT plasma [PDF]

open access: yes, 2021
LAUREA MAGISTRALEAl giorno d’oggi, la ricerca sulla fusione termonucleare controllata gioca un ruolo cruciale nella transizione energetica verso le fonti rinnovabili.
Aucone, Lorenzo
core  

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