Updates for automatic analysis and post-processing of JET neutral particle analysers for TT and DT campaigns

Sirén, P.; Beaumont, P.; Weisen, H.

doi:10.1088/1748-0221/17/08/c08006

Cited by 3 publications

(2 citation statements)

References 8 publications

(16 reference statements)

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“…Experimental evidence of fast ICRF-accelerated tritons was obtained via a neutral particle analyser [47] and an upgraded magnetic proton recoil (MPRu) spectrometer [48,49]. Figure 9 shows the time evolution of measured neutral particle fluxes of tritium at the energy of 143, 172 and 248 keV, which Ion temperature as measured by the impurity charge exchange diagnostic at ρtor ≈ 0.2 and on-axis electron temperature as given by electron cyclotron emission measurements as a function of total auxiliary input power (NBI + ICRH) in JET high performance D-T hybrid plasmas with different ICRH schemes in table 2.…”

Section: Experimental Observations Of Fast Tritonsmentioning

confidence: 99%

“…Neutral particle fluxes of tritium as the function of triton energy as measured by a neutral particle analyser [47] for discharges with different ICRH schemes are shown in figure 10. The neutral particle fluxes of tritium are strongest for second harmonic heating of T without 3 He gas injection, and they decrease when 3 He is injected for 3 He minority heating because less power is absorbed by tritium ions when 3 He is present (see section 4.6.1).…”

Section: Experimental Observations Of Fast Tritonsmentioning

confidence: 99%

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Experiments in high-performance JET plasmas in preparation of second harmonic ICRF heating of tritium in ITER

Mantsinen,

Jacquet,

Lerche

et al. 2023

Nucl. Fusion

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The reference ion cyclotron resonance frequency (ICRF) heating schemes for ITER deuterium–tritium (D-T) plasmas at the full magnetic field of 5.3 T are second harmonic heating of T and 3He minority heating. The wave-particle resonance location for these schemes coincide and are central at a wave frequency of 53 MHz at 5.3 T. Experiments have been carried out in the second major D-T campaign (DTE2) at JET, and in its prior D campaigns, to integrate these ICRF scenarios in JET high-performance plasmas and to compare their performance with the commonly used hydrogen (H) minority heating. In 50:50 D:T plasmas, up to 35% and 5% larger fusion power and diamagnetic energy content, respectively, were obtained with second harmonic heating of T as compared to H minority heating at comparable total input powers and gas injection rates. The core ion temperature was up to 30% and 20% higher with second harmonic T and 3He minority heating, respectively, with respect to H minority heating. These are favourable results for the use of these scenarios in ITER and future fusion reactors. According to modelling, adding ICRF heating to neutral beam injection using D and T beams resulted in a 10%–20% increase of on-axis bulk ion heating in the D-T plasmas due to its localisation in the plasma core. Central power deposition was confirmed with the break-in-slope and fast Fourier transform analysis of ion and electron temperature in response to ICRF modulation. The tail temperature of fast ICRF-accelerated tritons, their enhancement of the fusion yield and time behaviour as measured by an upgraded magnetic proton recoil spectrometer and neutral particle analyser were found in agreement with theoretical predictions. No losses of ICRF-accelerated ions were observed by fast ion detectors, which was as expected given the high plasma density of n e ≈ 7–8 × 1019 m−3 in the main heating phase that limited the formation of ICRF-accelerated fast ion tails. 3He was introduced in the machine by 3He gas injection, and the 3He concentration was measured by a high-resolution optical penning gauge in the sub-divertor region. The DTE2 experiments with 3He minority heating were carried with a low 3He concentration in the range of 2%–4% given the fact that the highest neutron rates with 3He minority heating in D plasmas were obtained at low 3He concentrations of ∼2%, which also coincided with the highest plasma diamagnetic energy content. In addition to 3He introduced by 3He gas injection, an intrinsic concentration of 3He of the order of 0.2%–0.4% was measured in D-T plasmas before 3He was introduced in the device, which is attributed to the radioactive decay of tritium to 3He. According to modelling, even such low intrinsic concentrations of 3He lead to significant changes in ICRF power partitioning during second harmonic heating of T due to absorption of up to 30% of the wave power by 3He.

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Section: Experimental Observations Of Fast Tritonsmentioning

confidence: 99%

Section: Experimental Observations Of Fast Tritonsmentioning

confidence: 99%

Experiments in high-performance JET plasmas in preparation of second harmonic ICRF heating of tritium in ITER

Mantsinen,

Jacquet,

Lerche

et al. 2023

Nucl. Fusion

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ICRH operations and experiments during the JET-ILW tritium and DTE2 campaigns

Jacquet,

Lerche,

Mantsinen

et al. 2023

AIP Conference Proceedings

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Overview of T and D–T results in JET with ITER-like wall

Maggi,

Abate,

Abid

et al. 2024

Nucl. Fusion

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In 2021 JET exploited its unique capabilities to operate with T and D-T fuel with an ITER-like Be/W wall (JET-ILW). This second major JET D-T campaign (DTE2), after DTE1 in 1997, represented the culmination of a series of JET enhancements – new fusion diagnostics, new T injection capabilities, refurbishment of the T plant, increased auxiliary heating, in-vessel calibration of 14MeV neutron yield monitors – as well as significant advances in plasma theory and modelling in the fusion community. DTE2 was complemented by a sequence of isotope physics campaigns encompassing operation in pure tritium at high T-NBI power. Carefully conducted for safe operation with tritium, the new T and D-T experiments used 1 kg of T (vs 100 g in DTE1), yielding the most fusion reactor relevant D-T plasmas to date and expanding our understanding of isotopes and D-T mixture physics. Furthermore, since the JET T and DTE2 campaigns occurred almost 25 years after the last major D-T tokamak experiment, it was also a strategic goal of the European fusion programme to refresh operational experience of a nuclear tokamak to prepare staff for ITER operation. The key physics results of the JET T and DTE2 experiments, carried out within the EUROfusion JET1 work package, are reported in this paper. Progress in the technological exploitation of JET D-T operations, development and validation of nuclear codes, neutronic tools and techniques for ITER operations carried out by EUROfusion (started within the Horizon 2020 Framework Programme and continuing under the Horizon Europe FP) are reported in [1], while JET experience on T and D-T operations is presented in [2].

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Updates for automatic analysis and post-processing of JET neutral particle analysers for TT and DT campaigns

Cited by 3 publications

References 8 publications

Experiments in high-performance JET plasmas in preparation of second harmonic ICRF heating of tritium in ITER

Experiments in high-performance JET plasmas in preparation of second harmonic ICRF heating of tritium in ITER

ICRH operations and experiments during the JET-ILW tritium and DTE2 campaigns

Overview of T and D–T results in JET with ITER-like wall

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