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Divertor Plates in Plasma Stream

#3703


Tests of Divertor Plate Mock-Ups under Energetic High-Temperature Plasma Stream

Tech Area / Field

  • FUS-MCS/Magnetic Confinement Systems/Fusion
  • FUS-PLA/Plasma Physics/Fusion

Status
3 Approved without Funding

Registration date
21.02.2007

Leading Institute
Budker Institute of Nuclear Physics, Russia, Novosibirsk reg., Akademgorodok

Supporting institutes

  • VNIITF, Russia, Chelyabinsk reg., Snezhinsk

Collaborators

  • Forschungszentrum Jülich GmbH, Germany, Jülich

Project summary

The Project goal is the development of plasma facing materials for magnetic fusion devices. Plasma flows with extreme parameters relevant for conditions of the largest existing and designed tokamaks can be produced in the GOL-3 linear device in Novosibirsk. In the GOL-3 device the plasma is confined in a 12 m long solenoid with corrugated magnetic field. Corrugation period is 22 cm and the ratio of the magnetic field in the corrugation cells is Bmax/Bmin=4.8/3.2 T.

The plasma with densities of 1020 – 1021 m-3 in the solenoid is heated by injection of a relativistic electron beam at one of the ends. Electron and ion temperature of the heated plasma is ~1-2keV and the confinement time is about 0.5 ms. Plasma exhaust from the ends of the device can be used to simulate plasma –wall interaction in fusion devices in a very broad range of plasma parameters including those during ELMs or major disruptions. Advantage of using the GOL-3 device is both high electron and ion temperatures in the plasma exhaust and rather high repetition rate ~ 1 pulse/20min.

It is proposed to perform extensive tests of plasma-facing components for burning plasma facilities at GOL-3 device under plasma streams with energy densities up to 20MJ/m2. Main activity will be directed to study the durability of advanced materials such as carbon and tungsten-based composites. Transport of the particles and vapor released from the wall into high-density high temperature plasmas and high-pressure wave generation in solids can be studied also using a comprehensive diagnostics set at the device. The results will be compared with model calculations and experimental data from TEXTOR and JET tokamaks.

In the framework of this program it is intended to design and construct a special end section of the GOL-3 device to carry out the proposed studies, and to develop the required diagnostics for tests of the pertor plate mock-ups. It is also proposes a s further increase of plasma parameters in the GOL-3 device that will be achieved by extension of the heating electron beam duration from 8 to 20 µs, by application of an auxiliary neutral beam heating system and development of a new electron beam system with pulse duration up to 100 µs. This increase of heating systems capacity will result in a significant increase of plasma parameters in the device and enable investigations even more fully to simulate plasma conditions during critical events in largest tokamaks.

The realization of the project will give important data about wall-plasma interaction and materials properties, required for creation of next generation of high-temperature plasma facilities.


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