Impurity behaviour in JET high-current baseline scenario for Deuterium, Tritium and Deuterium-Tritium plasmas

• The understanding of the causes that led to uncontrolled increase of P rad in DT plasmas, was one of the crucial issues. • DT and T baseline plasmas exhibit higher impurities content and intensity of W in comparison to D pulses. • It has been noted that a higher flat-top gas flow rate, results in a decrease of impurities content and plasma radiation. • Higher n e and P rad values, together with a less effective ELM flushing, may lead to an early termination of the pulse. To support future ITER operation, experimental campaigns at the Joint European Torus (JET) with an ITER-like wall (tungsten divertor and beryllium main chamber) in pure deuterium (D), tritium (T) and Deuterium-Tritium (D-T) were performed. One of the most important challenges in recent years was the development of two main scenarios that investigated different approaches to achieve the high fusion power as well as good plasma confinement (Garzotti et al., 2023). The first one, so-called baseline scenario is relying on high plasma current (I p ≈3.5 MA), normalized beta β N < 2 and safety factor q 95 ≈ 3 (Garzotti et al., 2023). On the other hand, the second one, so-called Hybrid scenario is operating at lower plasma current (flat-top I p ≤ 2.6 MA) and density with respect to the baseline, higher normalized beta β N > 2 and safety factor q 95 ≈ 4.8 (Hobirk et al., 2023). In this paper we focus on the impurity behaviour analysis for the baseline discharges at I p = 3.5 MA and B T = 3.3 T with D, T and DT plasmas, in which the gas and power waveform were optimized to achieve the best possible performance. In particular, we study the impact of total heating power (P tot + P alpha ), flat-top gas flow and ELM (edge localized modes) frequency on mid-Z (Nickel (Ni), Copper (Cu)) and high-Z (Tungsten (W)) impurities. In addition, we compared the two best performing pulses of the baseline scenario (I p = 3.5MA, B T = 3.3 T and P in ≈ 35 MW) in D and DT in order to identify the causes responsible for the increase in radiation during the DT pulse, which led to an early plasma termination. All presented results rely on the data collected by the VUV as well as the bolometry system. Detailed analysis indicates that in the baseline scenario, higher radiation, which is most likely due to the tungsten (W), is observed for T and DT plasmas in comparison to D. Moreover, for the two best performing baseline pulses, tomographic reconstructions show that the radiated power density is mainly emitted from the low field side (LFS) of the plasma and W does not accumulate in the plasma center (Telesca et al., 2024).

Authors

Institutions

Publication Details

Journal
Nuclear Materials and Energy
Published
2024-09-20
DOI
https://doi.org/10.1016/j.nme.2024.101743
Citations
3
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
1.98
Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Impurity behaviour in JET high-current baseline scenario for Deuterium, Tritium and Deuterium-Tritium plasmas

D. Frigione, E. Kowalska-Strzęciwilk, A. Chomiczewska, G. Telesca et al.
3 citations
Nuclear Materials and Energy
Magnetic confinement fusion research
1.98
article

Impurity behaviour in JET high-current baseline scenario for Deuterium, Tritium and Deuterium-Tritium plasmas

D. Frigione, E. Kowalska-Strzęciwilk, A. Chomiczewska, G. Telesca, N. Wendler, I. Ivanova‐Stanik, D. Van Eester, F. Rimini, L. Garzotti, V.K. Zotta, W. Gromelski, G. Pucella
article en
3 citations

Abstract

• The understanding of the causes that led to uncontrolled increase of P rad in DT plasmas, was one of the crucial issues. • DT and T baseline plasmas exhibit higher impurities content and intensity of W in comparison to D pulses. • It has been noted that a higher flat-top gas flow rate, results in a decrease of impurities content and plasma radiation. • Higher n e and P rad values, together with a less effective ELM flushing, may lead to an early termination of the pulse. To support future ITER operation, experimental campaigns at the Joint European Torus (JET) with an ITER-like wall (tungsten divertor and beryllium main chamber) in pure deuterium (D), tritium (T) and Deuterium-Tritium (D-T) were performed. One of the most important challenges in recent years was the development of two main scenarios that investigated different approaches to achieve the high fusion power as well as good plasma confinement (Garzotti et al., 2023). The first one, so-called baseline scenario is relying on high plasma current (I p ≈3.5 MA), normalized beta β N < 2 and safety factor q 95 ≈ 3 (Garzotti et al., 2023). On the other hand, the second one, so-called Hybrid scenario is operating at lower plasma current (flat-top I p ≤ 2.6 MA) and density with respect to the baseline, higher normalized beta β N > 2 and safety factor q 95 ≈ 4.8 (Hobirk et al., 2023). In this paper we focus on the impurity behaviour analysis for the baseline discharges at I p = 3.5 MA and B T = 3.3 T with D, T and DT plasmas, in which the gas and power waveform were optimized to achieve the best possible performance. In particular, we study the impact of total heating power (P tot + P alpha ), flat-top gas flow and ELM (edge localized modes) frequency on mid-Z (Nickel (Ni), Copper (Cu)) and high-Z (Tungsten (W)) impurities. In addition, we compared the two best performing pulses of the baseline scenario (I p = 3.5MA, B T = 3.3 T and P in ≈ 35 MW) in D and DT in order to identify the causes responsible for the increase in radiation during the DT pulse, which led to an early plasma termination. All presented results rely on the data collected by the VUV as well as the bolometry system. Detailed analysis indicates that in the baseline scenario, higher radiation, which is most likely due to the tungsten (W), is observed for T and DT plasmas in comparison to D. Moreover, for the two best performing baseline pulses, tomographic reconstructions show that the radiated power density is mainly emitted from the low field side (LFS) of the plasma and W does not accumulate in the plasma center (Telesca et al., 2024).

Nuclear Materials and EnergyVol. 41
National Agency for New Technologies, Energy and Sustainable Economic Development (IT), University of Rome Tor Vergata (IT), Culham Centre for Fusion Energy (GB), Culham Science Centre (GB), Institute of Plasma Physics and Laser Microfusion (PL), Sapienza University of Rome (IT)
Climate action
Openalex Percentile: Top 9%
Magnetic confinement fusion research
1.98
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.