Developments and Challenges in the Design of the ITER DRGA

Delabie, E.; Jepu, I.; Andrew, P.; Biewer, T. M.; Boyd, G. E.; Douai, D.; Hughes, S.; Kruezi, U.; Marcus, Chris; Neilson, H.; Rasmussen, D. A.; Ravelli, F. A.; Vartanian, S.; Contributors, Jet

doi:10.1109/tps.2022.3223648

Cited by 2 publications

(1 citation statement)

References 18 publications

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“…The D/T isotope ratio, as measured by the subdivertor penning gauge discharge spectroscopy [25,26], varied slightly between the pulses throughout the experiment, as shown in figure 9. The first pulse, #99960, had residual deuterium in the vessel walls and therefore the highest measured D/T ratio of about ∼18/82 at the beginning of the heating phase, decreasing towards 15/85 at the end of the discharge.…”

Section: The High Fusion Power T-rich Experiments In Jet Dte2mentioning

confidence: 98%

JET D-T scenario with optimized non-thermal fusion

Maslov,

Lerche,

Auriemma

et al. 2023

Nucl. Fusion

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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.

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Section: The High Fusion Power T-rich Experiments In Jet Dte2mentioning

confidence: 98%

JET D-T scenario with optimized non-thermal fusion

Maslov,

Lerche,

Auriemma

et al. 2023

Nucl. Fusion

View full text Add to dashboard Cite

show abstract

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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Developments and Challenges in the Design of the ITER DRGA

Cited by 2 publications

References 18 publications

JET D-T scenario with optimized non-thermal fusion

JET D-T scenario with optimized non-thermal fusion

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

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