Conceptual integrated approach for the magnet system of a tokamak reactor

Abstract In the framework of the reflexion about DEMO, a conceptual integrated approach for the magnet system of a tokamak reactor is presented. This objective is reached using analytical formulas which are presented in this paper, coupled to a Fortran code ESCORT (Electromagnetic Superconducting System for the Computation of Research Tokamaks), to be integrated into SYCOMORE, a code for reactor modelling presently in development at CEA/IRFM in Cadarache, using the tools of the EFDA Integrated Tokamak Modelling task force. The analytical formulas deal with all aspects of the magnet system, starting from the derivation of the TF system general geometry, from the plasma main characteristics. The design criteria for the cable current density and the structural design of the toroidal field and central solenoid systems are presented, enabling to deliver the radial thicknesses of the magnets and enabling also to estimate the plasma duration of the plateau. As a matter of fact, a pulsed version DEMO is presently actively considered in the European programmes. Considerations regarding the cryogenics and the protection are given, affecting the general design. An application of the conceptual approach is presented, allowing a comparison between ESCORT output data and actual ITER parameters and giving the main characteristics of a possible version for DEMO.

[1]  T. Ando,et al.  Pulsed operation test results of the ITER-CS model coil and CS insert , 2002 .

[2]  Jean Johner.  HELIOS: A Zero-Dimensional Tool for Next Step and Reactor Studies , 2011 .

[3]  J. Duchateau,et al.  Tore Supra Superconducting Toroidal Magnetic Field System , 2009 .

[4]  D. A. Humphreys,et al.  Commissioning and initial operation of KSTAR superconducting tokamak , 2009 .

[5]  H. Zohm,et al.  On the Minimum Size of DEMO , 2010 .

[6]  Osamu Mitarai,et al.  Design activities on helical DEMO reactor FFHR-d1 , 2012 .

[7]  P. Libeyre,et al.  The ITER Magnets: Design and Construction Status , 2012, IEEE Transactions on Applied Superconductivity.

[8]  Subrata Pradhan.  Status of SST-1 Refurbishment , 2010 .

[10]  Progress of plasma experiments and superconducting technology in LHD , 2006 .

[11]  L. Wegener,et al.  Status of Wendelstein 7-X construction , 2009 .

[12]  S. T. Wu,et al.  An overview of the EAST project , 2007 .

[13]  D. Bessette.  Design of a $\hbox{Nb}_{3}\hbox{Sn}$ Cable-in-Conduit Conductor to Withstand the 60 000 Electromagnetic Cycles of the ITER Central Solenoid , 2014, IEEE Transactions on Applied Superconductivity.

[14]  Henning Gruehagen,et al.  Measured Performance of Four New 18 kW@4.5 K Helium Refrigerators for the LHC Cryogenic System , 2004 .

[15]  M. Gadomska,et al.  Overview of EU DEMO design and R&D activities , 2014 .

[16]  A. Vostner,et al.  Status of ITER Conductor Development and Production , 2012, IEEE Transactions on Applied Superconductivity.

[17]  J. Duchateau,et al.  The ITER toroidal field model coil project , 2005 .

[18]  P. Hertout,et al.  Conceptual design for the superconducting magnet system of a pulsed DEMO reactor , 2013 .

[19]  G. Pásztor,et al.  Upgrade of operating range for SULTAN test facility , 2002 .

[20]  W. Fietz,et al.  Application of high temperature superconductors for fusion , 2011 .

[21]  L. Serio,et al.  CHALLENGES FOR CRYOGENICS AT ITER , 2010 .

[22]  Martin N. Wilson,et al.  Superconducting Magnets , 1984 .

[23]  T. Fujita,et al.  Status of JT-60SA tokamak under the EU-JA Broader Approach Agreement , 2008 .

[24]  Christian Bachmann,et al.  Neutronic analyses and tools development efforts in the European DEMO programme , 2014 .

[25]  S. Sackett.  EFFI: A code for calculating the electromagnetic field, force, and inductance in coil systems of arbitrary geometry , 1978 .

[26]  Richard J. Thome,et al.  MHD and fusion magnets: Field and force design concepts , 1982 .