FIRE, a novel concept of massive gas injection for disruption mitigation in ITER: Validation on Tore Supra

Saint‐Laurent, F.; Martín, G.; Alarcón, Tomás; Luyer, A. Le; Pastor, P.; Putvinski, S.; Vincent, Benoit; Bucalossi, J.; Brémond, S.; Moreau, Ph.; Nardon, E.; Reux, C.

doi:10.1016/j.fusengdes.2014.09.007

Cited by 5 publications

(4 citation statements)

References 41 publications

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“…Other physics dependencies related to the runaway losses are the magnetic fluctuations [20] or some plasma instabilities [21,22]. A number of methods to suppress runaways have been studied worldwide: resonant magnetic perturbations [12] or massive material injection [23][24][25][26][27]. Due to the difficulties with generating reliable and reproducible runaway electrons beams, only a few attempts have been made to try to suppress a fully-blown runaway electron beam [9,15].…”

Section: Introductionmentioning

confidence: 99%

Runaway electron beam generation and mitigation during disruptions at JET-ILW

Reux¹,

Plyusnin²,

Alper³

et al. 2015

Nucl. Fusion

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110

129

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Disruptions are a major operational concern for next generation tokamaks, including ITER. They may generate excessive heat loads on plasma facing components, large electromagnetic forces in the machine structures and several MA of multi-MeV runaway electrons. A more complete understanding of the runaway generation processes and methods to suppress them is necessary to ensure safe and reliable operation of future tokamaks. Runaway electrons were studied at JET-ILW showing that their generation dependencies (accelerating electric field, avalanche critical field, toroidal field, MHD fluctuations) are in agreement with current theories.

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Section: Introductionmentioning

confidence: 99%

Runaway electron beam generation and mitigation during disruptions at JET-ILW

Reux¹,

Plyusnin²,

Alper³

et al. 2015

Nucl. Fusion

Self Cite

110

129

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“…where T 0 is the temperature inside the capillary that we want to detect and γ H 2 = 7/5. In the shock regime, the Mach number Ma relates pressure, temperature, density and gas speed, as shown by the equations below [26,27]:…”

Section: Theorymentioning

confidence: 99%

Temperature analysis in the shock waves regime for gas-filled plasma capillaries in plasma-based accelerators

Biagioni¹,

Alesini²,

Anania³

et al. 2019

J. Inst.

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A: Plasma confinement represents a crucial point for plasma-based accelerators and plasma lenses because it can strongly affect the beam properties. For this reason, an accurate measurement of the plasma parameters, as plasma temperature, pressure and electron density, must be performed. In this paper, we introduce a novel method to detect the plasma temperature and the pressure for gasfilled capillaries in use at the SPARC_LAB test facility. The proposed method is based on the shock waves produced at the ends of the capillary during the gas discharge and the subsequent plasma formation inside it. By measuring the supersonic speed of the plasma outflow, the thermodynamic parameters have been obtained both outside and inside the capillary. A plasma temperature around 1.4 eV has been measured, that depends on the geometric properties and the operating conditions of the capillary. K: Plasma diagnostics -high speed photography; Wake-field acceleration (laser-driven, electron-driven); Accelerator Applications; Plasma diagnostics -charged-particle spectroscopy 1Corresponding author.

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“…Systems that use non-metallic vacuum seals, such as for opening a pressurized gas chamber, may be more sensitive to neutron damage. Concepts to reduce sensitivity to neutrons (such as rupture disks) [9], have been considered for MGI and would also need to be considered in a reactor employing SPI or EPI. The only non-metallic component in an EPI would be an insulator that is not a vacuum seal, and it should be possible to shield this component from neutrons.…”

Section: Alternate Systems Considered For Dms Applicationsmentioning

confidence: 99%

Prototype tests of the electromagnetic particle injector-2 for fast time response disruption mitigation in tokamaks

Raman¹,

Lunsford²,

Clauser³

et al. 2021

Nucl. Fusion

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Predicting and controlling disruptions is an important and urgent issue for ITER. Some disruptions with a short warning time may be unavoidable. For these cases, a fast time response disruption mitigation method is essential. Experimental tests on a prototype system of a novel, rapid time-response disruption mitigation system being developed for tokamak-based reactors and as a backup option for ITER, referred to as the electromagnetic particle injector (EPI), have been able to verify the primary advantages of the concept. These are its ability to meet short warning time scales of <10 ms while attaining the projected high velocities for deep radiative payload penetration in reactor-scale plasmas. The EPI relies on an electromagnetic propulsion system. A metallic sabot is accelerated electromagnetically to the required velocities (>1 km s−1) within 2 ms, at which point it releases a radiative payload consisting of a shell pellet or well-defined microspheres. Initial experimental tests from the prototype system show attainment of over 600 m s−1 in about 1 ms. Essential aspects of payload separation from the sabot and sabot capture have also been demonstrated at 200 m s−1, and the method can be extended to over 2 km s−1.

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FIRE, a novel concept of massive gas injection for disruption mitigation in ITER: Validation on Tore Supra

Cited by 5 publications

References 41 publications

Runaway electron beam generation and mitigation during disruptions at JET-ILW

Runaway electron beam generation and mitigation during disruptions at JET-ILW

Temperature analysis in the shock waves regime for gas-filled plasma capillaries in plasma-based accelerators

Prototype tests of the electromagnetic particle injector-2 for fast time response disruption mitigation in tokamaks

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