Numerical Evaluation of the Quench Behaviour of the ITER Toroidal Field Model Coil

  • R. Heller
  • J. L. Duchateau
  • S. Nicollet
  • F. Prat
Part of the Advances in Cryogenic Engineering book series (ACRE, volume 43)


In the frame of the ITER program, a Toroidal Field Model Coil is being built in Europe. Calculations about the thermohydraulic behaviour of this coil are presented in detail using the codes SARUMAN and GANDALF. The Helium temperature increase along the cooling circuits, the pressure drop and the mass flow partition inside the cable during normal operation will be discussed. One of the most crucial points is the behaviour of the coil during quench with a safety discharge. The general behaviour of the coil will be studied. Particular emphasis will be put on the pressure increase in case of a quench which in fact is strongly dependent on the dimensions of the joints and the external cryogenic circuit. The calculations and the resulting design choices for these parts are presented and discussed. An experimental program will be carried out to assess the validity of these choices as a necessary contribution to the ITER design.


Friction Factor Hydraulic Diameter Annular Region Toroidal Field International Thermonuclear Experimental Reactor 
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Copyright information

© Springer Science+Business Media New York 1998

Authors and Affiliations

  • R. Heller
    • 1
  • J. L. Duchateau
    • 2
  • S. Nicollet
    • 2
  • F. Prat
    • 2
  1. 1.Forschungszentrum KarlsruheInstitut für Technische PhysikKarlsruheGermany
  2. 2.Association Euratom/CEA CadaracheSt Paul Lez Durance CedexFrance

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