The Central Solenoid (CS) of a fusion reactor is expected to be operated ar
ound 13T, 5.8K, at ramp rates of 0.5-1 T/s. The present state of the art of
the superconductor technology allows the fulfillment of such requirements
only by means of coils made of Cable-In-Conduit Nb3Sn conductors (CICC). In
the ENEA Frascati laboratory, the construction of a CICC Nb3Sn coil (Im o.
d., 0.6m bore) was completed in 1994. Its original destination was the high
field DC test facility SULTAN. Since many characteristics of this coil mak
e it representative of a CS, it was decided that it was higher priority to
test it in transient field conditions. An ad-hoc facility was designed and
set up in the ENEA Frascati Laboratory. The tests performed can be divided
into four categories: 1. Ramp Rate Limitations; 2. AC loss measurement on t
he whole coil; 3. Current redistribution inside the conductor induced by fa
st ramps, 4. DC performance within the limits of the facility. Well known a
nd validated computer codes (SARUMAN and GANDALF) have been used both to pr
edict the behaviour of the coil and to interpret the results. In the paper
the results of all the tests are reported. Their influence on the design of
CICC coils is discussed.