Com optimitzar una matriu de dades? Utilitats bàsiques de l"SPSS

Una vegada es disposa de les dades introduïdes al paquet estadístic de l"SPSS (Statistical Package of Social Science) en una matriu de dades, és el moment de plantejar-se optimitzar aquesta matriu per poder extreure el màxim rendiment a les dades, segons el tipus d"anàlisi que es pretengui dur a terme. Per a això, el mateix SPSS té una sèrie d"utilitats que poden ser de gran utilitat. Aquestes utilitats bàsiques poden diferenciar-se segons la seva funcionalitat entre: les utilitats per a l"edició de dades, les utilitats per a la modificació de variables i les opcions d"ajuda que ens brinda. A continuació es presenten algunes d"aquestes utilitats

JT-60SA Magnet System Status

The JT-60SA experimental device will be the world’s largest superconducting tokamak when it is assembled in 2019 in Naka, Japan (R = 3 m, a = 1.2 m). It is being constructed jointly by institutions in the EU and Japan under the Broader Approach agreement. Manufacturing of the six NbTi equilibrium field (EF) coils, which have a diameter of up to 12 m, has been completed. So far, 13 of the 18 NbTi toroidal field (TF) coils, each 7-m high and 4.5-m wide, have also been manufactured and tested at 4 K in a dedicated test facility in France. The first three of four Nb3Sn central solenoid (CS) modules have been completed, as have all of the copper in-vessel error field correction coils. Installation of the TF magnet, around the previously welded 340° tokamak vacuum vessel and its thermal shield, started at the end of 2016 and is currently underway. The TF magnet will in turn support the EF and CS coils

Design Optimization and Assessment of Fabrication of ITER Central Solenoid Twin Box Joints

The ITER Central Solenoid (CS) will be one of the world's largest and most powerful pulsed superconducting electromagnet ever built; at an approximate weight of 1300 tons and a total height of 18 m consisting of a stack of six electrically independent 4.1 m diameter modules. In order to electrically connect the CS with the feeder busbars, 12 twin box joints are used to assure an efficient high current transfer while avoiding excessive AC losses. The fabrication of the box entails a succession of steps: explosion bonding of the stainless steel and the copper, precision machining of the internal part of the box and the cover, introduction of the conductor bundle followed by a controlled compaction to achieve the required void fraction, closure welding the cover onto the box, and subsequent reaction heat treatment (HT) for the formation of the Nb3Sn superconductor. The combined effect of all these fabrication processes, if not optimized, can lead to significant residual stresses and large localized plastic deformation acting during HT, which have empirically shown to result into microstructural heterogeneities and in the worst cases, cracking, and thereby component disqualification for use into a nuclear environment. The paper summarizes design optimizations investigated through mock-ups and could be implemented to remedy the present manufacturing fabrication technology process qualification failure(s). Various solutions have been realized by changing different design parameters whose effect on the response to the HT is studied. Dimensional metrology and residual stress measurements via hole - drilling method complemented with metallographic investigations were performed to assess the suitability of each of the solutions. Additionally, an innovative test bench is described, that was implemented for in - situ monitoring of a twin box mock ups during HT

JT-60SA Magnet System Status

The JT-60SA experimental device will be the world’s largest superconducting tokamak when it is assembled in 2019 in Naka, Japan (R=3m, a=1.2m). It is being constructed jointly by institutions in the EU and Japan under the Broader Approach agreement.Manufacturing of the six NbTi equilibrium field coils, which have a diameter of up to 12 m, has been completed. So far 13 of the 18 NbTi toroidal field coils, each 7 m high and 4.5 m wide, have also been manufactured and tested at 4 K in a dedicated test facility in France. The first three of four Nb3Sn central solenoid modules have been completed, as have all of the copper in-vesselerror field correction coils.Installation of the toroidal field magnet, around the previously welded 340° tokamak vacuum vessel and its thermal shield, started at the end of 2016 and is currently underway. The TF magnet will in turn support the EF and CS coils.25th International Conference on Magnet Technology (MT-25