VENECIA: Venecia software package for thermal hydraulic analysis of forced flow cooled superconducting equipment and their primary cryogenic subsystems

ITER. Toroidal Field Coil

Several global VENECIA models were developed for the latest ITER studies on transient thermohydraulic behaviour of the Toroidal Filed (TF) magnet system, Poloidal Field (PF) magnet system, Central Solenoid (CS) magnet system and Correction Coils magnet system with appropriate elements of their primary cryogenic circuits. The models were thoroughly treated for different plasma scenarios and operational modes.

The Toroidal Filed Coil (TFC) model together with the its cooling circuit allows detailed thermohydraulic simulations of the TFC winding pack and structure under different operational conditions including mitigation of pulsed heat load, plasma disruption and fast energy discharge.

Model features:

  • individual modelling of 14 cable in conduit conductors (CICC) in a 1-D approximation for the TF winding pack using a two-channel approach;
  • individual modelling of external pipes, cryolines, manifolds and heat exchangers in a 1-D approximation;
  • the total number of different 1-D objects exceeds 300;
  • detailed description of different transient heat loads over 1-D objects;
  • quasi-3D simulation of the TFC structures via 2D modelling of 32 cross-sections of the TF case with radial plates and insulation (the total number of mesh nodes exceeds 1,000,000);
  • detail description of different transient heat loads over 2D cross-sections;
  • modelling of pressure-mass flow rate characteristics of control valves and pumps;
  • modelling of a liquid helium bath.
Figure 1. TF coil hydraulic scheme used in VENECIA simulation of normal operation.
Figure 2. Temperature map for TF model cross-section 9 at 530s of reference plasma pulsing (repetitive mode).