JET experiments with tritium and deuterium–tritium mixtures

Horton, L. D.; Batistoni, P.; Boyer, H.; Challis, C.; Ćirić, D.; Donné, A. J. H.; Eriksson, L.‐G.; García, J.; Garzotti, L.; Gee, S.; Hobirk, J.; Joffrin, E.; Jones, Timothy; King, D.; Knipe, S.; Litaudon, X.; Matthews, G. F.; Monakhov, I.; Murari, A.; Nunes, I.; Riccardo, V.; Sips, A. C. C.; Warren, Robert J.; Weisen, H.; Zastrow, K.‐D.

doi:10.1016/j.fusengdes.2016.01.051

Cited by 22 publications

(14 citation statements)

References 88 publications

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“…Unfortunately, only a handful of experiments with tritium have been completed at JET so far, and the operational space is poorly explored. More information will be available once the tritium and DT experiments in the JET-ILW are performed [27].…”

Section: Discussionmentioning

confidence: 99%

Energy and particle confinement in JET H-mode plasma

et al. 2020

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This work describes the behaviour of the global energy and particle confinement on JET observed in a massive database of H-mode plasmas covering almost the whole lifetime of JET operations, both with the carbon and metal wall. The analysis is focused on type I ELMy H-modes in stationary phases. It is shown that plasma density in that regime is determined mainly by the plasma current, edge safety factor, triangularity of the last closed flux surface and the hydrogenic isotope mass. Behaviour is consistent for the whole database regardless of divertor configuration or the plasma facing materials. On average, thermal energy confinement time in JET with the carbon wall (JET-C) is accurately predicted by the IPB98(y,2) scaling. For JET with the ITER-like wall (JET-ILW), the energy confinement is found to be lower than expected from the scaling. The difference is found to be much stronger in a divertor configuration with the outer strike point at a vertical target and the pumping throat at the private flux. Observed lower confinement in JET-ILW can partially be attributed to the additional operational constraints of the metal wall machine, i.e. the avoidance of heavy impurity accumulation via additional gas dosing, but not fully. The isotope effect on the energy confinement in the Meff = 1–2 range is found to be the same in JET-C and JET-ILW, thus is independent of the wall material, if correlation with plasma density is accounted for. The effect of the toroidal magnetic field on the confinement is between zero and slightly negative. Triangularity has a generally favourable effect on the energy confinement, but the magnitude changes across the database. The effect of triangularity on plasma density is always much stronger than on energy confinement however, therefore plasmas with high triangularity are in general more dense and colder than at lower triangularities. The work described in this paper is completed under the EUROfusion global confinement database project, and the data shown here will be available to EUROfusion collaborators shortly. The data are also either already included in the international H-mode confinement database, or will be in the future updated version.

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Section: Discussionmentioning

confidence: 99%

Energy and particle confinement in JET H-mode plasma

et al. 2020

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“…In a final section it is shown, how this local outgassing from the upper inner divertor region induced by the plasma heating could be used to intentionally desorb the accumulated fuel desorption there. This could be useful for wall isotope control and fuel inventory reduction in future JET campaigns with T [29].…”

Section: Introductionmentioning

confidence: 99%

Impact of divertor configuration on recycling neutral fluxes for ITER-like wall in JET H-mode plasmas

Cal¹,

Losada²,

Aguilera³

et al. 2020

Plasma Phys. Control. Fusion

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It is well known since the last years that in JET, with the ITER-like wall, the performance of high-power Hmode plasmas strongly depends on the divertor magnetic topology. This is generally attributed to the effect of the magnetic field shaping on the neutral flux transport and pumping, which determine in high density H-mode plasmas the pedestal properties and finally the global confinement. In the present work we have analysed for different magnetic configurations the spatial distribution and the dynamic behaviour of the D emission. Experimental observations indicate that for certain configurations, the surface temperature and the D -emission anomalously increase on top of the inner divertor, which points to thermal outgassing there. This is the region where most Beryllium co-deposits accumulate and most Deuterium becomes trapped. The overheating at this region far from the strike point (SP) is observed to happen in magnetic configurations with reduced distance between the divertor material surface and the Separatrix (Clearance). The neutral flux that appears at the upper inner divertor during a few milliseconds after the ELM-crash, is by more than an order of magnitude larger than the puffing rate and dominates over the rest of the divertor recycling. Finally, a preliminary study describes how this thermal fuel outgassing from the co-deposited layers could be intentionally used as a Wall-conditioning technique with plasmas that focalise their particle and heat flux there. This could be used as a Wall isotope exchange technique or for Tritium recovery from regions where Be co-deposits accumulate in JET with the ITER-like wall.

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“…The JET-ILW D-T experimental campaign, by design, will address questions of interest to ITER operation, see for example [97]. Moreover, the development of the integrated scenarios needed to meet JET DTE2 goals, in itself, provided significant results for ITER operation preparation, in support of the ITER Research Plan, IRP [65].…”

Section: Preparation Of Integrated Scenarios For Jet's Upcoming D-t C...mentioning

confidence: 99%

“…The preparation for operations with tritium and D-T involved several plants and diagnostics refurbishments and enhancements over several years, as well as the preparation of improved procedures for safe operation with tritium [97]. These activities are generating valuable know-how of the operation of a nuclear tokamak in the European fusion community that will be useful for fusion power plants design, operation, tritium inventory and waste management, and for their related safety and regulatory requirements.…”

Section: Preparation For Tritium and D-t Operationsmentioning

confidence: 99%

“…These activities are generating valuable know-how of the operation of a nuclear tokamak in the European fusion community that will be useful for fusion power plants design, operation, tritium inventory and waste management, and for their related safety and regulatory requirements. Progress of this work was reported in [97,172] and references therein. sections 5.1 to 5.5 report only the final steps of the preparation and commissioning for T and D-T operation.…”

Section: Preparation For Tritium and D-t Operationsmentioning

confidence: 99%

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Overview of JET results for optimising ITER operation

et al. 2022

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The JET 2019-2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major Neutral Beam Injection (NBI) upgrade providing record power in 2019-2020, and tested the technical & procedural preparation for safe operation with tritium. Research along three complementary axes yielded a wealth of new results. Firstly, the JET plasma programme delivered scenarios suitable for high fusion power and alpha particle physics in the coming D-T campaign (DTE2), with record sustained neutron rates, as well as plasmas for clarifying the impact of isotope mass on plasma core, edge and plasma-wall interactions, and for ITER pre-fusion power operation. The efficacy of the newly installed Shattered Pellet Injector for mitigating disruption forces and runaway electrons was demonstrated. Secondly, research on the consequences of long-term exposure to JET-ILW plasma was completed, with emphasis on wall damage and fuel retention, and with analyses of wall materials and dust particles that will help validate assumptions and codes for design & operation of ITER and DEMO. Thirdly, the nuclear technology programme aiming to deliver maximum technological return from operations in D, T and D-T benefited from the highest D-D neutron yield in years, securing results for validating radiation transport and activation codes, and nuclear data for ITER.

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JET experiments with tritium and deuterium–tritium mixtures

Cited by 22 publications

References 88 publications

Energy and particle confinement in JET H-mode plasma

Energy and particle confinement in JET H-mode plasma

Impact of divertor configuration on recycling neutral fluxes for ITER-like wall in JET H-mode plasmas

Overview of JET results for optimising ITER operation

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