Publications de Pierluigi Bruzzone

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The magnetic field in a coil results in a transverse force on the strands pushing the cable towards one side of the jacket. A special cryogenic press has been built to study in a unique way the mechanical and electrical properties of full-size ITER Cable-in-Conduit (CIC) samples under a transverse, mechanical load. The press can transmit a variable (cyclic) force of at least 650 kN/m to a cable section of 400 mm at 4.2 K. The jacket around the cable is partly opened in order to transmit the transverse force

Knowledge of the actual Nb3Sn filaments' thermal strain, epsilon(th), in a cable-in-conduit conductor (CICC) is essential to predict the CICC performance in operation starting from the strand scaling laws for the critical current density J(c)(B, T, epsilon ...

This work presents the initial studies on the requirements for the design of 3D coils on EU-DEMO. The use of 3D coils in present machines includes two main purposes: the first one is the Error Field Correction (EFC). The EFC aims at minimizing the intrinsi ...

As a result of extremely high upper critical fields Bc2, high temperature superconductors (HTSs) have the potential to be used as high field insert coils in magnet systems where the background field is provided by low temperature superconductors (LTS). How ...

Five subsize NbTi cable-in-conduit conductors with parametric variations were fabricated and their DC performance was tested in the SULTAN facility. A comparison of the measured strand data and the cable performances clearly indicates that the current carrying capacity of the conductors is considerably reduced due to the self-field effect. This result reflects that because of the high transverse resistance the interstrand current sharing is not very efficient. Furthermore, the take-off electric field was fo

In the framework of ITER-EDA, a 13 T-46 kA Nb3Al conductor with stainless steel jacket has been developed in order to demonstrate applicability of an Nb3Al conductor with react-and-wind technique to ITER-TF coils. Using a 3.5 m sample consisting of a pair of conductors with 0% and 0.4% bending strain, the critical current performances of the Nb3Al conductors were studied to verify that the conductor achieves the expected performance and the bending strain of 0.4% does not originate degradation. The critical

We present the pre-concept design of the European DEMO Magnet System, which has successfully passed the DEMO plant-level gate review in 2020. The main design input parameters originate from the so-called DEMO 2018 baseline, which was produced using the PRO ...

During the test of ITER conductors at nominal conditions, a degradation of the current sharing temperature has been observed after electromagnetic cyclic loading. Rather than focusing on the microscopic phenomena at the origin of the degradation, the degra ...

A new series connected 25 T hybrid magnet system is being set up by the Helmholtz Zentrum Berlin (HZB) for neutron scattering experiments. CRPP has designed and manufactured a pair of 20 kA current leads for the powering of the outer superconducting coils of the hybrid magnet system. In connection with the test of joints for JT60SA, the current leads were tested at ENEA at low voltage up to a current of 18 kA. The mass flow rates required to cool the current leads at different currents measured in the test

The calculation of AC loss due to the control currents in ITER is a cumbersome task. The reason is that control transients require small field changes (0.1 T or less) at moderate frequency (up to 10 Hz), where effects of partial penetration of the filament ...

The ITER CICC will undergo a number of cool-down and warm-up cycles over the lifetime of the plant. The standard SULTAN based ITER conductor qualification test normally includes one thermal cycle in the test sequence. In many samples a performance degradation was observed following this thermal loading. In order to investigate the effect of multiple thermal cycles on the TF conductor short sample, additional repeated thermal cycles to liquid nitrogen temperature were carried out on the left leg of the CNTF3

In spring 2013, the Edipo facility of CRPP was commissioned. The dipole is powered via two 18 kA HTS current leads, designed and manufactured at CRPP. As part of the Edipo commissioning framework, the operational parameters of the leads were implemented in the control system. The in-situ tests were found to be in good agreement with the tests performed without a background field in 2011. The leads consist of a conduction cooled HTS module, made of AgMgAu/Bi-2223 stacks, and a wire bundle heat exchanger. The

Direct current tests performed in the past on the conductor samples of the toroidal field (TF) ITER coils revealed degradation of current sharing temperature, T-cs. The degradation progresses with repetitive electromagnetic loading, and also with thermal c ...

AC loss in the Nb3Sn cable-in-conduit conductors (CICC) usually decreases after the conductor undergoes electromagnetic cycling. This can be attributed to the increase of inter-strand resistance due to the detachment of the strand-bonding during cyclic loa ...

The aim of this paper is to present an up to date review of the status of the European DIPOle (EDIPO) project whose objective is to build a new facility to perform both DC and AC tests of large superconductor samples in high magnetic background field (up t ...

One of the design features which yet offers interesting margins for performance optimization of cable-in-conduit conductors (CICCs), is their geometry. For relatively small size Nb3Sn CICCs, operating at high electromagnetic pressure, such as those for the ...

Prototype conductors for the ITER magnets have been tested extensively in the SULTAN facility at CRPP in the last decade. The in-depth characterization of the high current carrying conductors provided a valuable feedback in the design, with performance optimization and cost reduction. From the transient stability results on full size, short length conductor samples, the temperature margin required to withstand the plasma disruption has been found to be much smaller than originally assumed. A comparison betw

The experiments of Cable-in conduit conductor (CICC) short samples with high proportion of segregated copper strands have been carried out in SULTAN facility last September. These experiments aimed to investigate transient stability and AC losses of CICC conductor coated with different resistive barriers (Pb-30Sn-2Sb or Ni plating on strands) and to check the design of PF and TF CICC for HT-7U magnets. The resistive barriers' influences on the stability and AC losses of CICC are evaluated. These experimenta

A short sample of the NbTi cable-in-conduit conductor (CICC) manufactured for the ITER PF insert coil has been tested in the SULTAN facility at CRPP. The short sample consists of two paired conductor sections, identical except for the sub-cable and outer w ...

In 2018, two structures have been proposed with the goal of replacing the magnetEDIPOthat stopped operating in 2016. These two solutions were designed to generate a field of 15 T on an aperture of 100 x 150 mm2 at 4.2 K by using Nb 3Sn superconducting Ruth ...

Pierluigi Bruzzone

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Magnetic and mechanical AC loss of the ITER CS1 model coil conductor under transverse cyclic loading

Measurement of Tc distribution in NbSn CICC

Studies on EU-DEMO 3D coils requirements and conceptual design for error field correction and plasma control

Quench studies of YBCO insulated and noninsulated pancake coils

DC performance of subsize NbTi cable-in-conduit conductors

Critical current test results of 13 T-46 kA Nb3Al cable-in-conduit conductor

The DEMO magnet system - Status and future challenges

Statistical analysis of the current-sharing temperature evolution in Nb3Sn cable-in-conduit-conductors for ITER

Results of the test of a pair of 20 kA HTS current leads

Computations of AC loss in the ITER magnets, during fast field transients

Effect of Thermal Loading on Nb3Sn CICC Performance

Operational experience in the use of 18 kA HTS current leads

T-cs degradation of ITER TF samples due to fast current discharges

Measurements of AC Loss Evolution in ITER TF Conductors

Status Report of the EDIPO Project

Successful performances of the EU-AltTF sample, a large size Nb3Sn cable-in-conduit conductor with rectangular geometry

Recent results from R&D on superconductors at CRPP

Test results and analyses of conductor short samples for HT-7U

Test results of the ITER PF insert conductor short sample in SULTAN

Magnetic and Mechanical 3-D Modelling of a 15 T Large Aperture Dipole Magnet