Titolo della tesi: Integrated Modelling of Plasma Scenarios for JET and JT-60SA Tokamaks: Validation and Predictions for Future JT-60SA Experiments
To accelerate the realisation of fusion energy, the Broader Approach (BA) agreement
was signed between the European Atomic Energy Community (Euratom) and
Japan in 2007. As part of this agreement, the Satellite Tokamak Program (STP)
included the construction of the superconducting tokamak JT-60SA in Naka, Japan,
which achieved its first plasma on the 23rd of October 2023. JT-60SA aims to address
key physics and engineering challenges essential for the development of future
demonstration power plants and to support the exploitation of ITER by mitigating
its operational risks and studying advanced plasma scenarios. Through JT-60SA
experiments, scientists will gain knowledge on how to operate a superconducting
tokamak.
Integrated modelling is essential for predicting and interpreting the behaviour of
thermonuclear plasmas by simultaneously simulating a variety of physical phenomena
that occur across different regions, each with its own distinct scales and geometries.
This approach can support the development of plasma scenarios to achieve the
desired experimental goals. The work presented in this thesis aims to contribute to
the scientific exploitation of JT-60SA by supporting through integrated modelling
the scenario development in view of its second operational phase (OP2), expected
to start in 2026. This will be the first operational phase in which high heating
power and enhanced diagnostics will be available. The JT-60SA target scenarios will
be developed in stages, starting with lower plasma currents, magnetic fields, and
auxiliary heating power. The present work provides the first prediction, performed
using advanced 1.5-dimensional transport codes, of the performance expected during
the second operational phase of JT-60SA.
The models used for JT-60SA predictions are validated against experiments conducted
at JET in 2023, aiming to develop a scenario with dimensionless parameters
as close as possible to those envisaged for JT-60SA. The aim of the experiments
was to establish a high-β scenario comparable to JT-60SA Scenario #4.2 (advanced
inductive) and Scenario #5.1 (non-inductive steady-state), while exploring the MHD
limits at various magnetic field strengths and NBI power levels. This experiment
provided a unique opportunity to test different transport models that have not been
extensively employed in scenarios with relatively high values of βN, allowing to
evaluate their performance in such conditions.
However, it is important to note that JET lacked the advanced current drive and
current density profile tailoring capabilities that will be available in JT-60SA, namely
the high energy off-axis Negative Neutral Beam Injection (N-NBI) and Electron
Cyclotron Resonance Heating (ECRH), making it challenging to replicate the exact
conditions expected in JT-60SA. In fact, the JET scenario analysed in this thesis
relied exclusively on NBI heating, as no ECRH power was installed. Furthermore, the
JET shaping capabilities were constrained, with an elongation (κ) limited to below
1.6 and a triangularity (δ) below 0.4, compared to the higher shaping parameters of
JT-60SA scenarios, which features κ ∼ 1.9 and δ ∼ 0.47.
The modelling has been performed with the JINTRAC suite of codes, coupled to
both semi-empirical (i.e. Bohm/gyro-Bohm and CDBM), and reduced first-principle
transport models (i.e. QuaLiKiz and TGLF), on three JET pulses at different
magnetic field (1.7, 2.0 and 2.4 T) and with varying Neutral Beam Injection power
(13.5, 16 and 19 MW, respectively).
Overall, the modelled plasma kinetic profiles and time traces exhibit good agreement
with the experimental data across all magnetic field levels, with the majority
of the modelled profiles falling within the experimental error bars. Among the
transport models employed, the Bohm/gyro-Bohm transport model exhibits the
best agreement, consistently providing an upper boundary for the prediction of
temperatures, βN, total plasma energy, and neutron rate. In contrast, the CDBM
model consistently provides a lower boundary for these key plasma parameters,
with experimental results consistently falling within the range predicted by the two
models. QuaLiKiz consistently overpredicts the electron density peaking across
all magnetic fields, whereas this behaviour is not observed in TGLF at 1.7 T and
2.0 T, and only begins to emerge at 2.4 T, although to a lesser extent than QuaLiKiz.
The JET DTE3 experimental campaign in 2023 presented a valuable opportunity
to evaluate the performance of the advanced high-β scenario at 2.4 T and
19 MW in a D-T plasma mixture. However, when conducted in D-T, the pulse
failed to achieve stable performance due to the presence of deleterious MHD activity
at the end of the ramp-up phase, which had not been observed in the reference
deuterium pulse. In order to avoid this, the NBI power was reduced to 16 MW to
achieve a stable deuterium shot. The discrepancy observed can be attributed to the
higher sputtering yield in D-T compared to D, which results in a modified radiation
profile and lower temperature peaking. These changes influence the evolution of
the central safety factor (q0), the normalised beta (βN), and the associated MHD
activity, ultimately impacting the plasma stability. In a subsequent deuterium
experimental campaign, the ramp-up phase was adjusted to replicate the βN and
q0 evolution observed in the unstable D-T shot. This was achieved by modifying
the electron density to influence temperature peaking, successfully reproducing the
same MHD activity of the unstable D-T shot. Unfortunately, the optimization of
the ramp-up phase could not be implemented in D-T due to limited experimental
time. However, to evaluate the potential performance achievable in D-T at higher
NBI power, JINTRAC extrapolations were performed, extrapolating the D pulse to
a D-T mixture and increasing the NBI power. These simulations were conducted to
estimate the achievable βN during the flat-top phase, assuming the deleterious MHD
activity could have been avoided through proper optimisation of the ramp-up phase.
Extrapolating D shots to a D-T mixture remains a significant challenge due to the
differences in transport behaviour arising from the varying isotope mass and the
distinct sputtering yields; accurately modelling the latter would necessitate complex
coupled core-SOL (scrape-off layer) simulations.
The JINTRAC integrated modelling framework was subsequently employed
to simulate the ramp-up and flat-top phases of the baseline and hybrid scenarios
envisioned for the second operational phase of JT-60SA (OP2). These simulations
provide valuable insights into the feasibility of achieving the target plasma parameters,
Team. Due to the good agreement achieved with the JET validation, as well as
its relatively low computational demand, the Bohm/gyro-Bohm semi-empirical
transport model has been chosen to predict JT-60SA scenarios.
The hybrid scenario was modelled at both 3.7 MA/2.28 T and 2.7 MA/1.7 T with
an auxiliary heating power of 19 MW by scaling down the plasma current, magnetic
field, density, and power from the reference METIS simulation at 3.5 MA/2.28 T
with 37 MW of heating power. Optimisation of the ramp-up phase with respect
to METIS was necessary to achieve a safety factor profile above one with a low
magnetic shear region at lower power. The optimisation indicates that a slower
current ramp-up in the initial phase (0.5 to 6 s), combined with earlier NBI injection
and a more rapid density increase, is required to maintain qmin > 1.
The scenario was evaluated at three different values of the Greenwald density
fraction (fGW = ne/nGW = 0.8, 0.6, 0.4). Results indicate that a hybrid-like q profile
can be sustained at fGW = 0.8 and 0.6 for the 3.7 MA case and at fGW = 0.8 for
the 2.7 MA case. At lower densities, hollow current density profiles and reversed
q-profiles occur due to the significant off-axis penetration of the Negative-NBI. A
solution was explored involving the use of only the upper injector unit. At 2.7 MA,
with fGW = 0.4 and 19 MW, values of βN = 3 are predicted, suggesting that
exploring the high-β regime of the advanced inductive scenario could be feasible
even during the initial research phase.
The baseline scenario envisaged for Operational Phase 2 (OP2) at 4.6 MA/2.28 T
(fGW = 0.4) has been modelled under various assumptions regarding the normalised
critical pressure gradient (αcrit) in the pedestal, which is directly linked to its
height. A scan of this parameter has been conducted based on results from the
EPED1 code, suggesting a higher temperature pedestal than that predicted by
METIS using scaling laws. Results show that increasing the pedestal temperature
at a fixed density leads to an increase in both the stored thermal energy and the
confinement enhancement factor (H98). Moreover, the core plasma kinetic profiles
scale proportionally with the pedestal increase, maintaining a consistent gradient in
the core region. A confinement factor of H98 = 1.07 is predicted at pped = 20 kPa,
with a βN = 1.8, typical of the baseline scenario, and a stored energy of around
10 MJ.
These results underscore the importance of an accurate model for predicting
both density and temperature in the pedestal, which is essential for reliably assessing
the performance of the scenario.
The thesis is organised as follows:
• In Chapter 1 the main approaches to fusion are presented. A brief history of
the JET and JT-60SA tokamaks is provided, alongside a detailed description
of their main characteristics. A comparison between the two devices highlights
how JET has contributed to the development of JT-60SA scenarios, and
how JT-60SA will build on reults of JET to further develop non-inductive
steady-state operations.
• Chapter 2 outlines the theoretical background of the transport simulations
performed in this work. A description of the models and of the JINTRAC
integrated modelling framework is also provided.
• In Chapter 3 the JET programme in support of JT-60SA is discussed. Experimental
results are summarised, and the validation of various transport
models across three pulses at different magnetic field strengths is explored.
Additionally, extrapolations to higher NBI power in Deuterium-Tritium (D-T)
scenarios are presented.
• Chapter 4 focuses on predictive modelling for the second operational phase
(OP2) of JT-60SA. The optimisation of the ramp-up phase of the hybrid
scenario is analysed, with particular attention to the impact of plasma current
ramp rate, density ramp velocity, and NBI heating timing on the safety factor
profile. The baseline scenario is also investigated, with emphasis on the effects
of pedestal assumptions on the predicted performance.
• In Chapter 5 the conclusions of the work are drawn, and potential future
research directions are outlined.