Development and Applications of Magnet Module for SYCOMORE CEA System Code

Zani, L.; Artaud, J.F.; Boutry, A.; Gallo, L. Di; Duchateau, J.L.; Hertout, P.; Kahn, S. J.; Piot, N.; Reux, C.; Said, J.; Torre, A.

doi:10.1109/tps.2018.2853677

Cited by 5 publications

(5 citation statements)

References 8 publications

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“…Among those possible we choose here to explore the height impact on superconductor quantity needed in order reach a given target flux, the external CS radius being fixed (TF radial built supposed frozen). This study, led with a system-code version of MADMACS-CS [24], is intended to check, with a given TF geometry, which room for choice is available to fix the CS height. The configuration considered was the one of DEMO 2015 [21] and, CS conductor being fixed at 55 kA as in [21], the CS height was increased by addition of pancakes while thickness was optimized by removing one layer when possible, i.e.…”

Section: Cs Magnet System Design Parametric Studymentioning

confidence: 99%

Progresses at CEA on EU demo reactor cryomagnetic system design activities and associated R&D

et al. 2019

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The EU DEMO reactor is expected to be among the first applications of fusion for electricity generation in the near future and the design of its magnet system is of central importance as driving power plant performance, budget and production efficiency. In this purpose activities were led by CEA in the framework of EUROfusion Consortium to contribute to the EU DEMO magnet system design. It encompassed design activities (dimensioning and development of associated modelling tools) with R&D (design and tests of mock-ups). The CEA design activity was mainly oriented towards Toroidal Field (TF) coils system to propose a conceptual option (pancake-wound, no radial plates) established with a semi-analytical CEA tool that considers the inter-dependent electromagnetic and mechanical behaviors. Then the proposed design is consolidated by detailed analyses: Thermo-hydraulics evaluation by coupling THEA, TRAPS and CAST3M softwares respectively for thermo-hydraulics, electromagnetic and thermal items. The outcomes obtained in normal and off-normal regimes are exposed and discussed in the paper; Mechanics evaluation with the most stressed zones identified and their criticity evaluated, in particular in the insulation zones. Design optimization analyses were conducted on jacket shape, together with investigations on the thermo-mechanic hotspot criterion. Further to the TF system, the central solenoid design was addressed and an optimization analysis will be presented and discussed. On another side, CEA also conducted R&D activities, mostly regarding the TF system with hydraulic tests at variable void fraction to explore its impact on helium friction and a full-scale TF conductor sample design and manufacture.

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Section: Cs Magnet System Design Parametric Studymentioning

confidence: 99%

Progresses at CEA on EU demo reactor cryomagnetic system design activities and associated R&D

et al. 2019

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“…Figures 10a and 10b show the result of the P elec,net and ∆t pulse linear regressions on Central Solenoidal (CS) and Toroidal Field (TF) magnets parameters described in [6], respectively. P elec,net appears to be entirely driven by the toroidal magnetic field on plasma axis (B T ).…”

Section: Magnetsmentioning

confidence: 99%

“…The dark green (blue) horizontal and vertical lines correspond to the P elec,net mean values computed on regular bins as well as the statistical uncertainties computed removing (including) the invalid designs, respectively. parameters described in [6], respectively. P elec,net appears to be entirely driven by the toroidal magnetic field on the plasma axis (B T ).…”

Section: Plasma Profiles No Invalid Designs Have Been Observedmentioning

confidence: 99%

“…It also calculates the shield thickness needed to protect the inner leg of the toroidal field coil from excessive neutron flux. The toroidal field coil (TF) is modelled [6] and the TF width necessary to generate the prescribed magnetic field on the plasma axis is deduced. The central solenoid (CS) magnet is sized to fit in the remaining space in the centre of the tokamak and is modelled [6] to calculate the generated flux, allowing the pulse duration to be estimated [2].…”

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confidence: 99%

“…The toroidal field coil (TF) is modelled [6] and the TF width necessary to generate the prescribed magnetic field on the plasma axis is deduced. The central solenoid (CS) magnet is sized to fit in the remaining space in the centre of the tokamak and is modelled [6] to calculate the generated flux, allowing the pulse duration to be estimated [2]. Stress calculations are performed for both CS and TF magnets to estimate the quantity of steel necessary to hold the stresses generated by the Lorentz forces, providing a coherent radial build for the two magnets.…”

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confidence: 99%

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