In fusion magnets, Cable-In-Conduit Conductors (CICCs) are foreseen, consis
ting of an outer conduit and an inner niobium-tin cable produced by a simul
taneous heat treatment. The heat treatment and the different thermal contra
ctions of the various conductor materials lead to prestress onto the niobiu
m-tin filaments during cool down, degrading the superconducting parameters
considerably. These parameters show, during external mechanical loading, a
maximum dependence on strain (epsilon). For example, the critical current (
I-c) of steel jacketed CICCs increases about by a factor of 2 at epsilon ap
proximate to 0.7 % and decreases again at further straining (B = 13 T, T =
4 K). This characteristic is reversible up to epsilon approximate to 1.2 %
in stressed and unstressed condition of the conductor. If the conductor is
plastically deformed at 4 K up to a remaining strain (epsilon(r)) and then
warmed up to 295 K, epsilon(r) decreases by about a factor of 5, which is c
oupled to a phase transition resulting to a change of volume in the microst
ructure of the steel conduit. This reduced epsilon(r) remains constant afte
r cooling to 4 K again (shape memory) and the critical current corresponds
to this decreased epsilon(r). In case of an accidentally over-straining of
a CICC, a further temperature cycle of 4 K --> 295 K --> 4 K would recover
I-c. Recovery strain results with different jacket materials (aged) of Type
316L, 316LN, Incoloy 908, and titanium are investigated.