Publications related to Reversed field pinch

Statistics of Test Results for the ITER Nb3Sn and NbTi Conductors in the SULTAN Facility

Pierluigi Bruzzone, Kamil Sedlák, Boris Stepanov, Rainer Wesche

The series production of Nb3Sn and NbTi cable-inconduit conductors (CICC) for the winding of various coils in the International Thermonuclear Experimental Reactor (ITER) magnet system is being completed in 2015. The tests of the ITER conductor samples are ...

Ieee-Inst Electrical Electronics Engineers Inc2016

Winding Pack Proposal for the TF and CS Coils of European DEMO

Pierluigi Bruzzone, Kamil Sedlák, Rainer Wesche

The design of the European DEMO, i.e., the future fusion tokamak planned after ITER, is being developed under the coordination of the EUROfusion Consortium. This paper reports the design optimization of the toroidal field (TF) winding pack and its correspo ...

2016

Lower hybrid current drive experiments with different launched wave frequencies in the EAST tokamak

Jian Wang, Joan Decker, Mingkui Wang, Fang Liu, Yong Yang

EAST has been equipped with two high power lower hybrid current drive (LHCD) systems with operating frequencies of 2.45 GHz and 4.6 GHz. Comparative LHCD experiments with the two different frequencies were performed in the same conditions of plasma for the ...

Amer Inst Physics2016

Plasma turbulence in the scrape-off layer of the ISTTOK tokamak

Paolo Ricci, Federico David Halpern, Rogério Manuel Cabete De Jesus Jorge

The properties of plasma turbulence in a poloidally limited scrape-off layer (SOL) are addressed, with focus on ISTTOK, a large aspect ratio tokamak with a circular cross section. Theoretical investigations based on the drift-reduced Braginskii equations a ...

American Institute of Physics2016

Design, Manufacture and Test of a 82kA React&Wind TF Conductor for DEMO

Pierluigi Bruzzone, Kamil Sedlák, Boris Stepanov, Rainer Wesche

The Toroidal Field Coils (TFC) of the EUROFusion DEMO reactor call for Nb3Sn conductor with high field and high current. Another major requirement is the cost effectiveness, to keep the ratio of investment to electric power in the same range of the competi ...

Ieee-Inst Electrical Electronics Engineers Inc2016

Overview of progress on the EU DEMO magnet system design

Pierluigi Bruzzone, Kamil Sedlák, Boris Stepanov, Rainer Wesche, Elena Gaio

The DEMO reactor is expected to be the first application of fusion for electricity generation in the near future. To this aim conceptual design activities are progressing in Europe (EU) under the lead of the EUROfusion Consortium in order to drive on the d ...

Ieee-Inst Electrical Electronics Engineers Inc2016

ICRH induced particle losses in Wendelstein 7-X

Jonathan Graves, Wilfred Anthony Cooper, David Pfefferlé, Jonathan Marc Philippe Faustin

Fast ions in W7-X will be produced either by neutral beam injection (NBI) or by ion-cyclotron resonant heating (ICRH). The latter presents the advantage of depositing power locally and does not suffer from core accessibility issues (Drevlak et al 2014 Nucl ...

Plasma Physics and Controlled Fusion2016

Density limit studies in the tokamak and the reversed-field pinch

Cristian Galperti, Nicola Vianello

The ITER scenarios and the project of DEMO involve stable operation above the Greenwald density, which justifies efforts to understand and overcome the density limit, this last observed as a disruptive termination of tokamak discharges and a thermal crash ...

International Atomic Energy Agency2015

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Reversed field pinch

Statistics of Test Results for the ITER Nb3Sn and NbTi Conductors in the SULTAN Facility

Winding Pack Proposal for the TF and CS Coils of European DEMO

Lower hybrid current drive experiments with different launched wave frequencies in the EAST tokamak

Plasma turbulence in the scrape-off layer of the ISTTOK tokamak

Design, Manufacture and Test of a 82kA React&Wind TF Conductor for DEMO

Overview of progress on the EU DEMO magnet system design

Neoclassical toroidal torque generation by auxiliary heating in non-axisymmetric tori

Characterisation of the properties of a negative hydrogen ion beam by several beam diagnostic techniques

ICRH induced particle losses in Wendelstein 7-X

Density limit studies in the tokamak and the reversed-field pinch

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Chat with Graph Search

Winding Pack Proposal for the TF and CS Coils of European DEMO

Overview of progress on the EU DEMO magnet system design

Statistics of Test Results for the ITER Nb3Sn and NbTi Conductors in the SULTAN Facility

Plasma turbulence in the scrape-off layer of the ISTTOK tokamak

Design, Manufacture and Test of a 82kA React&Wind TF Conductor for DEMO

Lower hybrid current drive experiments with different launched wave frequencies in the EAST tokamak

Neoclassical toroidal torque generation by auxiliary heating in non-axisymmetric tori

Characterisation of the properties of a negative hydrogen ion beam by several beam diagnostic techniques

ICRH induced particle losses in Wendelstein 7-X

Density limit studies in the tokamak and the reversed-field pinch