A. Louzguiti

ITER

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L. Zani

CEA Cadarache

A. Torre

CEA Cadarache

Frédéric Topin

Institut Universitaire des Systèmes Thermiques Industriels

S. Nicollet

CEA Cadarache

Benoît Lacroix

CEA Cadarache

B. Turck

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Q. Gorit

CEA Cadarache

J.L. Duchateau

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

R. Babouche

Aix-Marseille Université

C. Hoa

ITER

Cooperative Institutions

CEA Cadarache

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

National Institutes for Quantum and Radiological Science and Technology

Max Planck Institute for Plasma Physics

National Agency for New Technologies, Energy and Sustainable Economic Development

Culham Science Centre

Institut de Recherche sur la Fusion par Confinement Magnétique

ITER

Royal Military Academy

Fusion Academy

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Optimization of the Electromagnetic Design of the FCC Sextupoles and Octupoles

IEEE Transactions on Applied Superconductivity (2019)

A. Louzguiti Douglas Martins Araujo D. W. Pracht Marco Prioli E. Ravaioli

The future circular collider (FCC) will require 696 double-aperture lattice sextupoles, 9336 single-aperture sextupole corrector magnets, and 480 double-aperture octupoles. The tunnel length and the overall integrated field of the main dipoles have to be kept constant so that the FCC can both reach the specified center of mass collision energy and fit into the Geneva basin. Considering these criteria, any reduction in the length of the other magnets can be traded in exchange for a reduced dipole field, which would result in an overall cost saving for the FCC. However, to be able to reduce the length of these sextupole and octupole magnets, their local strength has to be maximized. Consequently, in this paper, we first explore the maximum achievable local strength for these different magnet types for both Nb-Ti and Nb3Sn wire technology taking into account circuit and protection criteria. We then select and present a preferred design based on an overall cost and complexity reduction for the FCC.

10.1109/tasc.2019.2892839

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Citations (4)

Mise en service cryogénique tokamak JT 60SA

F. Michel Christine Hoa L. Zani A. Louzguiti

Source

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Citations (0)

Thermo-Hydraulic Modeling of JT-60SA TF02 Coil and Feeder for First Operation Predictions

IEEE Transactions on Applied Superconductivity (2024)

J. Lorenzo A. Louzguiti L. Zani Francesca Cau M. Parody Guzmán

During the commissioning phase of JT-60SA magnet system, which included the cool-down in 2020 and the energization of the 18 Toroidal Field (TF) coils up to a nominal current of 25.7 kA in 2021, the combined helium flow issued from TF02 coil and feeder outlet showed a higher temperature profile than the one of the other TF coils when energized, pointing to the presence of an extra joint resistance in the TF02 and associated feeder circuit. To analyze this temperature excursion and the potential associated risks, the TF02 hydraulic circuit and feeder have been modelled with the thermo-hydraulic CryoSoft suite in the framework of a collaboration between Fusion for Energy and CEA. This paper describes the different numerical models developed along with simplifying analytical strategies, comprising detailed THEA models of the TF02 feeder and a model of the TF02 hydraulic circuit in FLOWER. These models consider the variable thermal and hydraulic geometry along the feeder length, include static and transient heat loads from different sources, and account for the heat exchange between the feeder and the TF02 Lateral Pancake at the feeder Terminal Joint (TJ), thus enabling a detailed description of the helium temperature variations in the system. In addition to the static energization load, the discharge of the Equilibrium Field coils has been modelled and its impact on the helium temperature at the outlet and feeder TJ analyzed. Model results show that the temperature excursion due to a faulty joint in the feeder should not put at risk the operation of TF02 coil.

Transient (computer programming)

Thermal hydraulics

Excursion

10.1109/tasc.2024.3358256

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Citations (1)

AC Losses in JT-60SA TF Magnet During Commissioning: Experimental Analysis and Modeling

IEEE Transactions on Applied Superconductivity (2022)

A. Louzguiti S. Davis Kazuma Fukui K. Hamada C. Hoa

During the integrated commissioning of JT-60SA tokamak, the Toroidal Field (TF) magnet has experienced fast current discharges which have induced AC losses in its winding packs (WP) and in its casings. Using the thermo-hydraulic sensors network installed at the inlet and outlet of the TF coils, we have performed enthalpy balances to estimate the transient heat loads generated by AC losses. In parallel, we have modeled the hysteresis and coupling losses produced in the WP and the eddy currents losses produced in the casings by such events. We then assess and discuss the consistency between these experimental and first theoretical analyses from the energy balance point of view.

Transient (computer programming)

10.1109/tasc.2022.3170291

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Citations (3)

Design of Radiation Hard Spare Units for the Orbit Corrector Dipoles of LHC

IEEE Transactions on Applied Superconductivity (2020)

A. Louzguiti T. Sahner Daniel Schoerling S. Sequeira Tavares A. Tsinganis

Due to the High Luminosity upgrade of the Large Hadron Collider (HL-LHC), the orbit corrector dipoles located just before the interaction points of the accelerator will receive significantly increased gamma radiation doses, i.e., up to 20 MGy over the HL-LHC lifetime. Since these magnets were not designed to withstand such high gamma doses, new MCBC and MCBY magnets have to be designed and produced using radiation hard impregnation insulation and materials. In this paper, we describe both the gamma radiation campaign we are performing to determine the radiation hardness of the present MCBC and MCBY magnets and the new design and technologies that we have selected for the manufacturing of radiation hard spare units. We also discuss the impact of failing MCBC and MCBY magnets on the LHC and the foreseen alternative solutions.

Spare part

Orbit (dynamics)

10.1109/tasc.2020.2972223

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Citations (3)

Dynamic simulation of the first cool down of the JT-60SA cryo-magnet system

Cryogenics (2022)

F. Michel François Bonne Kazuma Fukui K. Hamada Christine Hoa

Shields

Fusion power

10.1016/j.cryogenics.2022.103537

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Citations (3)

ITER Central Solenoid Insert Test Results

IEEE Transactions on Applied Superconductivity (2016)

N. Martovetsky Takaaki Isono D. Bessette Yoshikazu Takahashi Y. Nunoya

The ITER central solenoid (CS) is a highly stressed magnet that must provide 30 000 plasma cycles under the ITER prescribed maximum operating conditions. To verify the performance of the ITER CS conductor in conditions close to those for the ITER CS, the CS insert was built under a USA-Japan collaboration. The insert was tested in the aperture of the CSMC facility in Naka, Japan, during the first half of 2015. A magnetic field of up to 13 T and a transport current of up to 60 kA provided a wide range of parameters to characterize the conductor. The CS insert has been tested under direct and reverse charges, which allowed a wide range of strain variation and provided valuable data for characterization of the CS conductor performance at different strain levels. The CS insert test program had several important goals as follows. 1) Measure the temperature margin of the CS conductor at the relevant ITER CS operational conditions. 2) Study the effects of electromagnetic forces and strain in the cable on the CS conductor performance. 3) Study the effects of the warmup and cooldown cycles on the CS conductor performance. 4) Compare the conductor performance in the CS insert with the performance of the CS conductor in a straight hairpin configuration (hoop strain free) tested in the SULTAN facility. 5) Measure the maximum temperature rise of the cable as a result of quench. The main results of the CS insert testing are presented and discussed.

Insert (composites)

Solenoid

10.1109/tasc.2016.2517322

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Citations (45)

Development of an Analytical-Oriented Extensive Model for AC Coupling Losses in Multilayer Superconducting Composites

IEEE Transactions on Applied Superconductivity (2016)

A. Louzguiti L. Zani D. Ciazynski B. Turck Frédéric Topin

Previous analytical models of ac coupling losses in multifilamentary composites under a time-varying external magnetic field were developed for specific strand geometries. Therefore, no global expression of coupling losses was established for any circular geometry. The purpose of this paper is, thus, to present the general analytical strategy and the assumptions of the model developed at CEA. Furthermore, coupling losses are generally characterized by a global time constant nτ.In this paper, effective coefficients (analogous to time constants) are developed to reflect the coupling between the different layers. A global linear equation system linking the amplitudes of the electric field in each layer and their time variation and that of the external magnetic field is deduced, establishing a coupling matrix built with time constant coefficients. In addition to the physical interpretation of the quantities defined, the global equation is numerically solved. Local fields are quantified, as well as currents and ac coupling losses in different types of composites. A better physical understanding of the composite is tentatively achieved by the use of this analytical model.

Coupling constant

Constant (computer programming)

Matrix (chemical analysis)

10.1109/tasc.2016.2529846

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Citations (9)

Thermal Hydraulic Analysis of JT-60SA TFC02 Complementary Quench Tests in CTF

IEEE Transactions on Applied Superconductivity (2022)

Q. Gorit S. Nicollet Benoît Lacroix A. Louzguiti Frédéric Topin

In the framework of JT-60SA tokamak commissioning (Japan, 2021), the 20 Toroidal Field Coils (TFC) were tested at the Cold Test Facility (CTF) at CEA-Saclay (France, 2018) and submitted to quench acceptance test (quench temperature up to 7.5 K at nominal current). Some complementary quench tests were performed on the spare coil TFC02, with different conditions, especially reduced current (at 75% and 50% of nominal current) and delayed quench detection (holding time of 0.5 s instead of 0.1 s). A numerical model was developed, with SuperMagnet (fortran, CryoSoft) coupling THEA (Thermohydraulic and electric 1-D physics of Cable In Conduit Conductor, CICC) and Flower (Thermohydraulic model of cryogenic network). The measurements are presented and compared to simulation results. The acceptance quench test of TFC02 depicted a maximal helium temperature of 27 K. During complementary quench tests, delayed quench detection induced higher helium temperature of 37 K. At 75% and 50% of nominal current, a so called “smooth” quench occurred. It is characterized by slow quench propagation and low resistive voltage which increase the quench propagation time required before triggering current discharge although it reduces the Joule energy dissipated by the coil.

Cryogenics

10.1109/tasc.2022.3171738

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Citations (1)

JT-60SA TF coil quench model and Analysis: Joule energy estimation with SuperMagnet and STREAM

Cryogenics (2022)

Q. Gorit S. Nicollet Benoît Lacroix A. Louzguiti A. Torre

Joule (programming language)

Thermal hydraulics

Resistive touchscreen

10.1016/j.cryogenics.2022.103454

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Citations (3)