Publications de Pierluigi Bruzzone

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The ITER toroidal field model coil (TFMC) was designed, constructed and tested by the European Home Team in the framework of the ITER research and development program of the Engineering Design Activities (EDA). The project was performed under the leadershi ...

Two short lengths of the full-size NbTi cable-in-conduit (CIC) conductor used to fabricate the ITER poloidal field coil insert were tested in the SULTAN facility. The two investigated conductors, otherwise identical, are distinguished only by the presence ...

A number of pressure drop measurements have been carried out at CRPP on a section of ITER cable-in-conduit conductor, using pressurized water at room temperature. The longitudinal friction factor is deduced for the strand bundle area and the central hole. Two layouts of radial helium inlet have been investigated and the measured radial pressure drop is assessed in terms of the equivalent conductor length producing the same pressure drop in axial direction. (C) 2001 Elsevier Science B.V. All rights reserved.

A spare, 3.5 m long dual-channel cable-in-conduit conductor (CICC) section, made according to the most recent ITER toroidal-field coil design, allowed conducting dedicated thermo-hydraulic experiments in the SULTAN test facility. The sample was heated by e ...

Various techniques have been proposed in order to assemble coated conductor tapes into high current strands. In this work, the preparation of high current capacity round strands starting from industrial coated conductors has been investigated. Round, twist ...

The integration of the feeder system in a tokamak involves complex engineering, manufacturing and logistics issues. Therefore, within the pre-conceptual design activities of the European DEMO fusion reactor, it is important to provide a preliminary sizing ...

The Poloidal Field (PF) coils of the International Thermonuclear Experimental Reactor (ITER) are designed using of NbTi cable-in-conduit conductors carrying a current up to 45 kA. Each PF coil consists of several modules Wound in double pancakes. Joints co ...

Two Nb3Sn cable-in-conduit conductors have been manufactured with identical non-Cu cross sections and the stabilizer either included in the Nb3Sn composite or partly segregated as copper wires. The two conductors are series connected and wound as a bifilar, single layer solenoid! assembled in the high field bore (11 T) of the SULTAN test facility. Beside the De: and AC losses characterization, the key tests include stability under pulsed transversal field (dB/dt up to 180 T/s), at DC operating current up to

An evolution of the contact resistances (R-c) of two full-size ITER (International Thermonuclear Experimental Reactor) cable-in-conduit conductors (CICC) aimed for the Poloidal Field Conductor Insert (PFCI) was studied in the Twente Cryogenic Press. The co ...

Future high-field accelerator magnets foresee the extensive use of Nb3Sn, more expensive than the Nb-Ti of LHC. For projects involving the series production of magnets, conductor grading is mandatory in order to reduce the cost. To allow grading ...

For large cable-in-conduit conductors, a current unbalance among the strands may be the reason for reduced performance in both de and pulsed operation, The resistance distribution of the strands at the conductor termination has been investigated as the kev parameter controlling the current distribution in operation, A Nb3Sn cable-in-conduit conductor consisting of 144 Cr plated strands has been used to prepare two terminations, one of them filled with low. resistivity solder. The resistance distribution res

Within the EFDA technology program, CRPP designed and prepared a short length of full size Nb3Sn developmental conductor to be tested in the SULTAN test facility. Nb3Sn strand with a higher specification and low Cu:non-Cu ratio was supplied by Outokumpu. Half of the produced wire length has been Cr-plated half was left bare. Subsequently, two Ti-jacketed cable-in-conduit conductors based on a braid as the first stage, have been manufactured by VNIIKP. After reaction heat treatment, the annular space of the

In response to the 2013 Update of the European Strategy for Particle Physics (EPPSU), the Future Circular Collider (FCC) study was launched as a world-wide international collaboration hosted by CERN. The FCC study covered an energy-frontier hadron collider ...

The Iter TF joints are of a twin-box design and the critical parameters of the overall resistance are 1) the contact between cable and termination, and 2) the resistance between two terminations. This paper describes applicability of non-destructive examin ...

The SULTAN test facility has been pivotal in qualifying forced-flow conductors in the last three decades. However, the rising demand for conductors for high-field magnets calls for a test facility able to provide a background magnetic field beyond the 11 T ...

The CONDOPT (CONDuctor OPTimization) experiment has been recently completed in SULTAN. The current sharing behavior of Nb-3 Sn samples was assessed as a function of the number of cyclic loads experienced during current sweeps in a 10 T background field. We present here results of a computer analysis performed with the code THEA(TM) (for consistent Thermal, Hydraulic and Electric Analysis) in support of the interpretation of the experimental results. We focus in particular on the critical current and current

For the new test facility EDIPO (European DIPOle), to be hosted by CRPP, two 18 kA HIS current leads were manufactured and successfully tested. The HTS module, made of AgMgAu/Bi-2223 tapes, is cooled only by heat conduction to the cold end, while the coppe ...

In the frame of the conceptual design studies for the Toroidal Field (TF) coils of DEMO, a solution based on a layer-wound magnet, rectangular-shaped Cable-in-Conduit conductors and W&R manufacturing approach, is being developed. The feasibility and perfor ...

In addition to a reduced number of feeders, which would simplify their integration in the cryostat of the tokamak, the present study considers the possibility to reduce the voltage during safety discharge of the toroidal field (TF) coils. A lowered dischar ...

A 13 T-46 kA Nb3Al conductor with steel jacket has been developed in the framework of ITER-EDA. The thermal strain will appear on the Nb3Al strands after heat treatment, when the steel jacket is used because of difference in their thermal expansion. The conductor critical current performance is degraded by this process. The critical current performance of this conductor was then studied to verify no degradation during the fabrication and small deterioration in the critical current performance even when the

Pierluigi Bruzzone

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The ITER toroidal field model coil project

Analyses and implications of V-I characteristic of PF insert conductor sample

Pressure drop and helium inlet in ITER CS1 conductor

Helium Flow and Temperature Distribution in a Heated Dual-Channel CICC Sample for ITER

Fabrication Trials of Round Strands Composed of Coated Conductor Tapes

A design proposal for the European DEMO superconducting bus bars and current leads

A low cost joint for the ITER PF coils, design and test results

Test results of SeCRETS, a stability experiment about segregated copper in CICC

Effect of cyclic loading and conductor layout on contact resistance of full-size ITER PFCI conductors

Progress on Tests on Splices Between Nb3Sn Rutherford Cables for Graded High-Field Accelerator Magnets

Contact resistance distribution at the termination of cable-in-conduit conductors

An alternative CICC design aimed at understanding critical performance issues in Nb3Sn conductors for ITER

FCC-hh: The Hadron Collider: Future Circular Collider Conceptual Design Report Volume 3

Applicability of Non-Destructive Examination to Iter TF Joints Nb3Sn

Conceptual Design of the EDIPO 2 Magnet

Application of the code THEA to the CONDOPT experiment in SULTAN

Test results of the 18 kA EDIPO HTS current leads

Design and Characterization of the Interlayer Joint Between Low-Field Nb3Sn Conductors of a Layer Wound DEMO TF Coil

Parametric study of the TF coil design for the European DEMO

Evaluation of critical current performance of 13 T-46 kA steel jacketed Nb3Al conductor