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

Schneider, M.; Lerche, E.; Eester, D. Van; Hoenen, O.; Johnson, T.; Mitterauer, Verena; Pinches, S. D.; Polevoi, A.; Poli, E.; Reich, M.

doi:10.1088/1741-4326/ac34d8

Cited by 16 publications

(15 citation statements)

References 26 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The fundamental ICRF heating of D ions described here, on the other hand, does not rely on the presence of D beam ions and could be used either in T-rich plasmas (with a fraction of Deuterium) to directly enhance fusion reactivity in RF only machines or in 50/50 D/T plasmas to produce core ion heating in thermonuclear reactors. It is applicability for ITER is currently under study [59].…”

Section: Discussionmentioning

confidence: 99%

JET D-T scenario with optimized non-thermal fusion

Maslov,

Lerche,

Auriemma

et al. 2023

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

In JET deuterium-tritium (D-T) plasmas, the fusion power is produced through thermonuclear reactions and reactions between thermal ions and fast particles generated by neutral beam injection (NBI) heating or accelerated by electromagnetic wave heating in the ion cyclotron range of frequencies (ICRFs). To complement the experiments with 50/50 D/T mixtures maximizing thermonuclear reactivity, a scenario with dominant non-thermal reactivity has been developed and successfully demonstrated during the second JET deuterium-tritium campaign DTE2, as it was predicted to generate the highest fusion power in JET with a Be/W wall. It was performed in a 15/85 D/T mixture with pure D-NBI heating combined with ICRF heating at the fundamental deuterium resonance. In steady plasma conditions, a record 59 MJ of fusion energy has been achieved in a single pulse, of which 50.5 MJ were produced in a 5 s time window (P fus = 10.1 MW) with average Q = 0.33, confirming predictive modelling in preparation of the experiment. The highest fusion power in these experiments, P fus = 12.5 MW with average Q = 0.38, was achieved over a shorter 2 s time window, with the period of sustainment limited by high-Z impurity accumulation. This scenario provides unique data for the validation of physics-based models used to predict D-T fusion power.

show abstract

Section: Discussionmentioning

confidence: 99%

JET D-T scenario with optimized non-thermal fusion

Maslov,

Lerche,

Auriemma

et al. 2023

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

show abstract

“…While in [3] the code GRAY was used, on AUG the code TORBEAM [8] is used. Both codes differ in the description of the Gaussian beam, but have been successfully bench marked for ITER [11]. In particular we set up TORBEAM to use the same absorption routine by D. Farina.…”

Section: Comparison With Linear Theorymentioning

confidence: 99%

Quantification of X3 absorption for ITER L-mode parameters in ASDEX Upgrade

Stober

Schubert²,

Schneider³

et al. 2023

EPJ Web Conf.

Self Cite

View full text Add to dashboard Cite

For an early H-mode access in hydrogen, ITER considers operating at 1/3 of the full field using 170 GHz X-Mode for heating at the 3rd harmonic. The optical thickness for such a heating scheme depends on Te2. It is rather low in the ohmic phase (with Te about 1-2 keV), but reaches high single pass absorption for the strongly EC heated plasma with Te exceeding 10 keV. Launching ECRH into an ohmic plasma may trigger a boot-strap process on Te if the additional power absorption due to increasing Te exceeds the additional power losses due to increased transport (which often tends to increase with input power). In this contribution we present measurements of the X3 absorption for the parameter range relevant for ITER, i.e. ne 2 1019 m−3, Te 2 keV in order to back up theoretical estimates used for the modeling so far. In ASDEX Upgrade (AUG) such low densities cannot be reached in H-mode such that dominant heating with NBI is not an option. For moderate Te, it is also not an option to use X3 heating as main heating, due to the excessive stray radiation threatening in-vessel components. This dilemma is solved with the 2-frequency EC system of AUG. The main central heating is done with the lower frequency of 105 GHz at the 2nd harmonic and full single pass absorption. Up to 3.5 MW of ECRH are used at that frequency to vary Te. Two other gyrotrons are used at 140 GHz to probe the X3 interaction close to the plasma center with a sequence of short blips. The expected values of single pass absorption are calculated with TORBEAM and vary from 7% to 70%. Below 40% single pass absorption the non-absorbed power triggers an arc in the tile gaps of the inner heat shield which screens the thermo-couples from the incoming beam such that they cannot be used. Between 40% and 80% single pass absorption, the predictions and measurements agree within the uncertainty of the measurement, unless we have clear evidence for non-linear interactions, which are not described by TORBEAM and which are not expected in ITER, but are due to some specific experimental choices for an isolated subset of our results.

show abstract

“…In IMAS, EC modelling can be carried out 1) as a standalone program, or 2) within the IMAS H&CD workflow where all H&CD sources can be combined together including synergetic effects [8], or 3) within a transport suite of codes. The best way to insure modularity and self-consistency of a scenario computation is to run EC modelling inside the H&CD workflow within a transport solver.…”

Section: Ec In Standalone and Within Integrated Modelling Contextsmentioning

confidence: 99%

New modelling capabilities to support the ITER EC H&CD System optimisation and preparation of plasma operation

Preynas

Schneider²,

Arroyo³

et al. 2023

EPJ Web Conf.

Self Cite

View full text Add to dashboard Cite

The ITER Electron Cyclotron Resonance Heating (ECRH) & Current Drive (ECCD) system is planned to be progressively installed and commissioned following the four stage approach of the ITER Research Plan. Starting with an injection of up to 5.8 MW from one Upper Launcher (UL) in the vacuum vessel to assist the plasma breakdown during First Plasma (FP) operation, the system will then be extended to achieve a capability of 20 MW injected power in Pre-Fusion Plasma Operation (PFPO) and Fusion Power Operation (FPO) phases. Development of optical modelling was required to characterize the optical performance of the FP configuration with the so-called First Plasma Protection Components. An optical 3D model using Zemax OpticStudio® has been developed and extended to the UL. Effects of higher order modes, thermal deformations and tolerances on the UL functionality have been characterized and are presented. Finally, in preparation of plasma operation and in the frame of the EC system upgrade layout optimisation, ECRH-ECCD modelling is being undertaken within the ITER Integrated Modelling and Analysis (IMAS) suite.

show abstract

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

Cited by 16 publications

References 26 publications

JET D-T scenario with optimized non-thermal fusion

JET D-T scenario with optimized non-thermal fusion

Quantification of X3 absorption for ITER L-mode parameters in ASDEX Upgrade

New modelling capabilities to support the ITER EC H&CD System optimisation and preparation of plasma operation

Contact Info

Product

Resources

About