Abstract
A helium inlet and dummy joint between conductors are one of the most important elements of the winding pack of the ITER PF -1 coil double pancakes. A helium inlet is used for letting liquid helium into the PF-1 coil conductor. A full-scale helium inlet sample for fatigue tests and the respective tooling were designed and manufactured. Fatigue tests of the full-scale helium inlet sample were conducted in accordance with ITER requirements testing parameters in order to check the fatigue strength of the structure. Before the fatigue tests thermo-cycling of the helium inlet in the temperature range of 77 to 293 K was conducted. Before and after the fatigue tests the leak tightness of the full-scale helium inlet sample was validated by the vacuum chamber method. A low ohm electrical joint is used to connect two NbTi «CICC» conductors of PF-1 coil into a single electrical loop. To qualify the design and technology of manufacturing of the electrical joint, a full-scale dummy joint sample was developed for fatigue tests at 77 K. The main design feature of the full-scale dummy joint sample for fatigue tests is a symmetrical model of two dummy joint samples with simultaneous loading to compensate the bending moment. Fatigue tests of the full-scale helium inlet sample at 77 K have been successfully conducted in 2013. Fatigue tests of the full-scale dummy joint sample will be conducted in 2014. This paper represents the results of calculating the stress-strain state of the symmetrical model of the full-scale dummy joint sample for fatigue tests with the prescribed loading and strain, the work on designing the symmetrical model of the dummy joint sample for fatigue tests and the test facility for conducting fatigue tests at 77 K. Also the results of the leak tightness tests and thermo-cycling of the full-scale helium inlet and the results of it fatigue tests at 77 K, are presented.
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