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In the frame of the international thermonuclear engineering reactor (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 circuits, the pressure drop and the mass flow repartition inside the cable during normal operation are discussed. One of the most crucial points is the behaviour of the coil during a quench propagation followed by a safety discharge. The general behaviour of the coil is studied during this event. Particular emphasis is placed on the pressure increase in case of a quench. This pressure increase is in fact in strong relation with the dimensioning of the joints and of the external cryogenic circuit. The calculations and the resulting design choices for these parts are presented and discussed.

Additional information

Authors: HELLER R, CEA, CEN Cadarache, Saint-Paul-lez-Durance (FR);DUCHATEAU J L, CEA, CEN Cadarache, Saint-Paul-lez-Durance (FR);NICOLLET S, CEA, CEN Cadarache, Saint-Paul-lez-Durance (FR)
Bibliographic Reference: Article: Advances in Cryogenic Engineering (1997)
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