Pre-conceptual studies and R&amp;D for DEMO superconducting magnets

Bruzzone, Pierluigi

doi:10.1016/j.fusengdes.2013.12.031

Cited by 17 publications

(5 citation statements)

References 4 publications

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“…These include low-temperature superconducting magnets (LTSC); plasma heating technologies like Neutral Beam Injection (NBI), Electron Cyclotron Heating (ECH), Ion Cyclotron Heating (ICH); pellet injection, vacuum and tritium processing (except tritium recovery from the blanket). In most of these areas, modest R&D is foreseen in the conceptual design phase of DEMO, aiming mainly at design and performance optimization (e.g., see [15]). …”

Section: Design Readiness and Strategy For Critical Technologies For mentioning

confidence: 99%

Overview of EU DEMO design and R&D activities

Federici¹,

Kemp²,

Ward³

et al. 2014

Fusion Engineering and Design

290

192

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Section: Design Readiness and Strategy For Critical Technologies For mentioning

confidence: 99%

Overview of EU DEMO design and R&D activities

Federici¹,

Kemp²,

Ward³

et al. 2014

Fusion Engineering and Design

290

192

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“…Regarding the details of the CICC designs, they are described in [153]: a first option reproduces the main characteristics of the EU-AltTF CICC, but with some additional technical features: a VF inside the cable bundle as low as about 25%, for maintaining a good Nb 3 Sn strand support, is retained; given a conductor hydraulic length of about 510 m, as compared to the 380 m of the ITER TF one, a pressure relief channel needs to be maintained (in the EU-AltTF proposal this was removed). A central steel perforated tube is presently considered, the thickness of which should be large enough to sustain the severe round-to-rectangular compaction conditions, without collapsing.…”

Section: Cicc Optimization Margins For Low Temperature Superconductorsmentioning

confidence: 99%

Cable-in-conduit conductors: lessons from the recent past for future developments with low and high temperature superconductors

Muzzi

Marzi

Zenobio

et al. 2015

Supercond. Sci. Technol.

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We review progress in the design of high field superconducting cable-in-conduit conductors (CICCs) for fusion applications, with special attention to the results of recent key experiments, leading to the state-of-the-art CICC technology: the ITER Toroidal Field and Central Solenoid programs, the EFDA Dipole conductor development program, the NHFML Hybrid Magnet project, the EU-TF Alt conductor demonstration, and the CRPP React & Wind flat cable test. For these projects, the main CICC design driver was the mitigation of Nb 3 Sn conductor performance degradation with electro-magnetic loading cycles. This was achieved by proper choice of cable layout and of conductor geometry, depending on the specific operating conditions and project requirements. In all cases, the necessity to limit cable movements inside the conductor jacket was identified to be of crucial importance. The main aspects of CICC manufacture are also discussed here, at least for what is the experience gained by the authors in both CICC jacketing and cabling processes. Finally, the state of the art of high-temperature superconducting (HTS) cables is discussed: at present, this technology is still in its infancy, but it is highly likely that major technological improvements could eventually lead to a widespread use of HTS CICCs.

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“…As an example, the Korean project (K-DEMO) is focusing on a tokamak with 6.5 m major radius, a peak toroidal field of 16 T and a toroidal field at plasma centre of 7.72 T [63], whereas the present design of the European tokamak (EU-DEMO) foresees a major radius of 9.0 m, a peak field of 13.6 T and a field at plasma center of 6.8 T [64]. In table 2 the main features of the TF magnetic systems of ITER and EU-DEMO are reported [65]. The challenging requirements of DEMO design open an issue on the superconductive materials to be used for magnets.…”

Section: Superconducting Magnets For Fusion Reactorsmentioning

confidence: 99%