Impact and mitigation of disruptions with the ITER-like wall in JET

Lehnen, M.; Arnoux, G.; Brezinsek, S.; Flanagan, J.; Gerasimov, S.; Hartmann, N.; Hender, T. C.; Huber, A.; Jachmich, S.; Kiptily, V.; Kruezi, U.; Matthews, G. F.; Morris, J.; Plyusnin, Victor F.; Reux, C.; Riccardo, V.; Sieglin, B.; Vries, P. C. de; Contributors, Jet

doi:10.1088/0029-5515/53/9/093007

Cited by 94 publications

(129 citation statements)

References 22 publications

Supporting

Mentioning

125

Contrasting

Order By: Relevance

“…is likely due to the fact that the fastest IDDB current quenches occur in DIII-D, which has entirely carbon plasma facing components (PFC) that are known to emit significant amounts of carbon impurity into the plasma during the thermal quench (TQ) [47]. The distribution for natural disruptions skews significantly towards longer € Δt cq for beryllium first wall and tungsten divertor devices, as has recently been reported for the ITER-like wall in JET [51] (data not presently available in IDDB) , and is expected to do so in ITER as well.…”

mentioning

confidence: 85%

The ITPA disruption database

et al. 2015

Self Cite

View full text Add to dashboard Cite

Abstract.A multi-device database of disruption characteristics has been developed under the auspices of the International Tokamak Physics Activity magneto-hydrodynamics topical group. The purpose of this ITPA Disruption Database (IDDB) is to find the commonalities between the disruption and disruption mitigation characteristics in a wide variety of tokamaks in order to elucidate the physics underlying tokamak disruptions and to extrapolate toward much larger devices, such as ITER and future burning plasma devices. In contrast to previous smaller disruption data collation efforts, the IDDB aims 2 to provide significant context for each shot provided, allowing exploration of a wide array of relationships between pre-disruption and disruption parameters. The IDDB presently includes contributions from nine tokamaks, including both conventional aspect ratio and spherical tokamaks. An initial parametric analysis of the available data is presented. This analysis includes current quench rates, halo current fraction and peaking, and the effectiveness of massive impurity injection. The IDDB is publicly available, with instruction for access provided herein.3

show abstract

mentioning

confidence: 85%

The ITPA disruption database

et al. 2015

Self Cite

View full text Add to dashboard Cite

show abstract

“…The dynamics of the unmitigated disruptions with the ILW is found to be different with respect to the C-wall [7]. In this context, it was found that mitigation by Massive Gas Injection became a necessity for ILW operations at plasma currents higher than 2.0 MA [8].…”

Section: Jet-past and Expected Performancementioning

confidence: 96%

Risk Mitigation for ITER by a Prolonged and Joint International Operation of JET

et al. 2015

View full text Add to dashboard Cite

Prolonged operation of the Joint European Torus (JET) in a set-up involving all ITER partners will be beneficial for ITER. Experiments at JET with its ITER-like wall and using a D-T plasma mixture will help to mitigate risks in the ITER research plan. Training of the ITER operators, technicians and engineers at JET will safe valuable time when ITER comes into operation. Moreover, the way in which the future ITER experiments will be organized can already be experienced at JET, by imposing a similar organisational structure. This paper will present arguments in favour of an extension of JET and additionally briefly discuss a number of enhancements that will make experiments on JET even more relevant for ITER.

show abstract

“…Successful disruption mitigation [46][47][48] with massive gas injection of a mixture of argon and deuterium has been obtained and is now mandatory for JET operation above 2 MA. The radiation efficiency of massive gas injection using the disruption mitigation valve (DMV) on JET (using a mixture of 90%D 2 +10%Ar) is 90% at a low thermal energy fraction W th /W mag of < 0.3 (where W th is the thermal energy and W mag is the magnetic stored energy), and reduces to 70% radiation efficiency at W th /W mag ∼ 0.5.…”

Section: Disruptions and The Generation Of Resmentioning

confidence: 99%

Overview of the JET results

Romanelli¹,

Abhangi²,

Abreu³

et al. 2015

Nucl. Fusion

View full text Add to dashboard Cite

Since the installation of an ITER-like wall, the JET programme has focused on the consolidation of ITER design choices and the preparation for ITER operation, with a specific emphasis given to the bulk tungsten melt experiment, which has been crucial for the final decision on the material choice for the day-one tungsten divertor in ITER. Integrated scenarios have been progressed with the re-establishment of long-pulse, high-confinement H-modes by optimizing the magnetic configuration and the use of ICRH to avoid tungsten impurity accumulation. Stationary discharges with detached divertor conditions and small edge localized modes have been demonstrated by nitrogen seeding. The differences in confinement and pedestal behaviour before and after the ITER-like wall installation have been better characterized towards the development of high fusion yield scenarios in DT. Post-mortem analyses of the plasma-facing components have confirmed the previously reported low fuel retention obtained by gas balance and shown that the pattern of deposition within the divertor has changed significantly with respect to the JET carbon wall campaigns due to the absence of thermally activated chemical erosion of beryllium in contrast to carbon. Transport to remote areas is almost absent and two orders of magnitude less material is found in the divertor.

show abstract

Impact and mitigation of disruptions with the ITER-like wall in JET

Cited by 94 publications

References 22 publications

The ITPA disruption database

The ITPA disruption database

Risk Mitigation for ITER by a Prolonged and Joint International Operation of JET

Overview of the JET results

Contact Info

Product

Resources

About