A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

Soukhanovskii, V.

doi:10.1088/1361-6587/aa6959

Cited by 59 publications

(45 citation statements)

References 157 publications

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“…The magnetic field configurations can be used for distribution of plasma transient event power around a larger region on the divertor plate to decrease the surface heating. Relocating the strike points with the divertor plates remote from the core plasma is another possible solution to avoid excessive surfaces overheating 24 , 25 . Development a separate divertor chamber may also change this problem and could eliminate the certain high-Z plasma drift and penetration trough the LCFS reducing core plasma contamination 26 .…”

Section: Discussionmentioning

confidence: 99%

New proposed ITER divertor design using carbon insert on tungsten to mitigate ELMs and secondary radiation effects on nearby components

Sizyuk

Hassanein

2022

Sci Rep

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Building a successful device for the magnetic fusion energy production is a great challenge. ITER is an international project of the tokamak based magnetic fusion design being developed for the demonstration of the feasibility of thermonuclear technologies for future realization of successful commercial fusion energy. A key obstacle to a successful magnetic fusion energy production is however, the performance during abnormal events including plasma disruptions and edge-localized modes (ELMs). A credible reactor design must tolerate at least a few of these transient events without serious consequences such as melting of the structure. This paper investigates and compares the performance of the current ITER tokamak design during two types of transient events, i.e., ELMs occurring at normal operation and disruptions during abnormal operation. We simulated the divertor components response using our integrated 3D HEIGHTS package. The simulations include self-consistent modeling of the interaction of the released core plasma particles with the initial solid divertor material, energy deposition processes, vaporization of divertor material, secondary plasma formation and MHD evolution, incident core particles collisions and scattering from this dense secondary plasma, photon radiation of secondary plasma, and the resulting heat loads on nearby components. Our simulations showed that using a small carbon insert around the strike point can significantly reduce the overall expected damage on the tungsten dome structure, reflector plates, and prevent tungsten vaporization and its potential core plasma contamination.

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Section: Discussionmentioning

confidence: 99%

New proposed ITER divertor design using carbon insert on tungsten to mitigate ELMs and secondary radiation effects on nearby components

Sizyuk

Hassanein

2022

Sci Rep

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“…Such magnetic configurations and designs allow to distribute the incident core plasma particles over a wider area on the divertor surface and therefore, decrease the heat loads on the divertor plate. Another possible solution for the divertor design is to move the divertor plates and strike points farther from the core plasma 4 , 25 . Designing a special divertor chamber as described in Ref.…”

Section: Issues With Iter Divertor Designmentioning

confidence: 99%

Potential design problems for ITER fusion device

Hassanein

Sizyuk

2021

Sci Rep

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The international thermonuclear experimental reactor (ITER) is a worldwide project currently being built in France for the demonstration of the feasibility of thermonuclear technologies for future realization of successful commercial fusion energy. ITER is of the tokamak based design using strong magnetic fields to confine the very hot plasma needed to induce the fusion reaction. Tokamak devices are currently the front leading designs. Building a successful magnetic fusion device for energy production is of great challenge. A key obstacle to such design is the performance during abnormal events including plasma disruptions and so-called edge-localized modes (ELMs). In these events, a massive and sudden release of energy occurs quickly, due to loss of full or partial plasma confinement, leading to very high transient power loads on the reactor surface boundaries. A successful reactor design should tolerate several of these transient events without serious damages such as melting and vaporization of the structure. This paper highlights, through comprehensive state-of-the-art computer simulation of the entire ITER interior design during such transient events, e.g., ELMs occurring at normal operation and disruptions during abnormal operation, potential serious problems with current plasma facing components (PFCs) design. The HEIGHTS computer package is used in these simulations. The ITER reactor design was simulated in full and exact 3D geometry including all known relevant physical processes involved during these transient events. The current ITER divertor design may not work properly and may requires significant modifications or new innovative design to prevent serious damage and to ensure successful operation.

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“…Introducing C in SOLPS. The future fusion device ITER [48] is planned to be run with the high confinement mode [49,50] and highly radiative divertor regime [51], where the upstream collisionality of the SOL plasma is ν * ≈ 15, corresponding to the density scan case with n u = 1.0 × 10 19 m −3 above. However, the coupling simulation with pure deuterium plasmas doesn't result in a large temperature drop.…”

Section: Activating Carbon Impuritiesmentioning

confidence: 99%

SOLPS simulations with electron kinetic effects

Zhao

Chankin

Coster

2019

Plasma Phys. Control. Fusion

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Power exhaust is one of the critical issues for tokamak edge plasma research. Electron kinetic effects may play an important role in future fusion devices. The KIPP code was coupled to a 1D version of SOLPS with an iterative algorithm [1, 2] to study the kinetic effects in a systematic way. The KIPP-SOLPS coupling algorithm allows us to incorporate kinetic electrons into the already sophisticated fluid model (B2) self-consistently. The KIPP-SOLPS coupling simulation results with pure deuterium and with carbon impurity in 1D geometry with stagnation point upstream and target downstream are presented. These results are then compared to the results of SOLPS simulations with different flux limiters. It shows that non-local electron parallel transport contributes to the non-Maxwellian tails of electrons near the target which reduces the electron target temperature. However, the non-Maxwellian tail has negligible impacts on deuterium ionization.

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A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

Cited by 59 publications

References 157 publications

New proposed ITER divertor design using carbon insert on tungsten to mitigate ELMs and secondary radiation effects on nearby components

New proposed ITER divertor design using carbon insert on tungsten to mitigate ELMs and secondary radiation effects on nearby components

Potential design problems for ITER fusion device

SOLPS simulations with electron kinetic effects

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