Predictive study of current sharing temperature test in the Toroidal Field Model Coil without LCT coil using the M&M code

Abstract The Toroidal Field Model Coil (TFMC) will be tested next year at Forschungszentrum Karlsruhe, Germany, in the frame of the International Thermonuclear Experimental Reactor (ITER). The TFMC is pancake-wound on radial plates using 10 Nb 3 Sn two-channel cable-in-conduit conductors, jointed on the inner- and outer-side of the coil. The drivers for the test of current sharing temperature ( T cs ) are the resistive heaters located on the inlet plumbing to each conductor (DP1.1, DP1.2) of the first double pancake (DP1). Since all available sensors are outside the coil, T cs in the conductor must be measured indirectly, which requires sophisticated analysis tools because of the complexity of the system. In the present work we use the recently developed Multi-conductor Mithrandir (M&M) code. The main aim of the paper is of assessing computationally possible scenarios of normal zone initiation in the high field region of the conductor, without quench propagation out of the inlet joint, in the test configuration without LCT coil.

[1]  L. Savoldi,et al.  Friction factor correlation with application to the central cooling channel of cable-in-conduit super-conductors for fusion magnets , 2000, IEEE Transactions on Applied Superconductivity.

[2]  C. Marinucci,et al.  The hydraulic solver Flower and its validation against the QUELL experiment in SULTAN , 1999, IEEE Transactions on Applied Superconductivity.

[3]  Laura Savoldi,et al.  Thermal-Hydraulic Analysis of Tcs Measurement in Conductor 1A of the ITER Central Solenoid Model Coil using the M&M Code , 2000 .

[4]  Laura Savoldi,et al.  Simulation of Thermal-Hydraulic Transients in Two-Channel CICC with Self-Consistent Boundary Conditions , 2000 .

[5]  J. R. Miller,et al.  A model for the prediction of Nb/sub 3/Sn critical current as a function of field, temperature, strain, and radiation damage , 1990 .

[6]  S. Nicollet,et al.  Dual channel cable in conduit thermohydraulics: Influence of some design parameters , 2000, IEEE Transactions on Applied Superconductivity.

[7]  D. Ciazynski,et al.  Test results and analysis of two European full-size conductor samples for ITER , 2000, IEEE Transactions on Applied Superconductivity.

[8]  Laura Savoldi,et al.  M&M: Multi-conductor Mithrandir code for the simulation of thermal-hydraulic transients in superconducting magnets , 2000 .

[9]  N Mitchell,et al.  Steady state analysis of non-uniform current distributions in cable-in-conduit conductors and comparison with experimental data , 2000 .

[10]  Roberto Zanino,et al.  A two-fluid code for the thermohydraulic transient analysis of CICC superconducting magnets , 1995 .

[11]  E Salpietro,et al.  The Test Facility for the ITER TF Model Coil , 1998 .

[12]  R. Zanino,et al.  Joint+conductor thermal-hydraulic experiment and analysis on the full size joint sample using MITHRANDIR 2.1 , 2000, IEEE Transactions on Applied Superconductivity.

[14]  R. Zanino,et al.  Heat slug propagation in QUELL. Part I: Experimental setup and 1-fluid GANDALF analysis , 1999 .

[15]  C. Marinucci,et al.  Predictive quench initiation analysis of the ITER TF model coil , 2000 .

[16]  E. Hatchadourian Stability and Control of Supercritical Helium Flow in the LHC Circuits , 2000 .

[17]  R. Zanino,et al.  Heat slug propagation in QUELL. Part II: 2-fluid MITHRANDIR analysis , 1999 .