Mechanical performance evaluation of the CFETR central solenoid model coil design

Liu, Xiaogang; Wang, Zhaoliang; Ren, Yong; Li, Junjun; Yin, Di; Li, Lei; Gao, Xiang; Wang, Yu

doi:10.1088/1741-4326/aa9866

Cited by 15 publications

(3 citation statements)

References 15 publications

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“…Also in the public sector, the United Kingdom (UK), likely because of its leaving the EU, is developing a Spherical Tokamak for Energy Production (Culham Centre for Fusion Energy 2020 ) due to deliver grid-connected electricity in 2040, as is a UK private sector company with its own spherical tokamak design, Tokamak Energy. Meanwhile, the Chinese are due to start constructing the China Fusion Engineering Test Reactor in the 2020s, also with the aim of electricity production around 2040 (Liu et al 2017 ). While both these national machines can be cast as “DEMO”-phase ITER successor machines, General Fusion, the Canadian national offering, a commercial company with significant state backing, is aiming to leapfrog ITER with a burning plasma in the 2020s and a grid-connected commercial prototype in the 2030s (Day 2020 ).…”

Section: Towards a “Burning Plasma” Event Via The Iter Demo Phase Andmentioning

confidence: 99%

Towards Fusion Energy in the Industry 5.0 and Society 5.0 Context: Call for a Global Commission for Urgent Action on Fusion Energy

Carayannis

Draper²,

Bhaneja³

2020

J Knowl Econ

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This article provides a high-level review of the geopolitical status quo of nuclear fusion energy and outlines a vision for the future against the backdrop of Industry 5.0 and Society 5.0. In 2020, the year of the 75th anniversary of Hiroshima and Nagasaki, ITER, the world’s largest fusion experiment, began its machine assembly, and next year, the DEMO (fusion power) stage of ITER planning is formally due to begin. With several countries now engaged in the design of DEMO-phase machines, we stress that a “burning plasma” self-sustaining fusion reaction event will be a critical juncture similar in status to the Trinity Test. In response, urging the need for US geopolitical engagement, we call for a “Global Commission for Urgent Action on Fusion Energy,” to be backed by the International Atomic Energy Agency and International Energy Agency (IEA), along the lines of the existing IEA “Global Commission for Urgent Action on Energy Efficiency.” We see the Commission serving a similar, this time international, role to the 1946 “Acheson-Lilienthal” report for fission and involving a global External Independent Review of the state-of-the art of fusion energy technologies. We suggest major “soft power” co-chairs from the Global West and North and from the Global South, thereby providing a geopolitical pivot which can unlock tens of billions of dollars in funding for multiple technology pathways, create a global regime to safeguard Intellectual Property, accelerate the transition from fossil fuels to a “Future Fusion Economy,” and prevent the geopolitical polarization of fusion energy.

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Section: Towards a “Burning Plasma” Event Via The Iter Demo Phase Andmentioning

confidence: 99%

Towards Fusion Energy in the Industry 5.0 and Society 5.0 Context: Call for a Global Commission for Urgent Action on Fusion Energy

Carayannis

Draper²,

Bhaneja³

2020

J Knowl Econ

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“…Material properties retrieved from the ITER database are used for the analysis [25][26][27]. 316 LN stainless steel is utilized for the coil case, support structures and the conductor jackets.…”

Section: Materials Properties and Load Conditionsmentioning

confidence: 99%

Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors

Liu

Wang

et al. 2020

Nucl. Fusion

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A comprehensive research facility project was approved in December 2018 with funding of 345 million EUR, to support the research and development of the China Fusion Engineering Test Reactor (CFETR). As part of this project, a full-size CFETR toroidal field (TF) coil will be designed, manufactured and tested by the Institute of Plasma Physics Chinese Academy of Sciences. Two options are being explored in parallel for the TF coil design, using either circle-in-square or rectangular cable-in-conduit conductors (CICCs). The rectangular CICC has been reported to have some merits for a DEMO TF coil, as reported in designs of the EU-DEMO and K-DEMO. First this paper presents the progress in the conceptual design of the CFETR TF coil with rectangular CICCs, according to the most recent reference single-null configuration and radial build of CFETR. Then, electromagnetic analyses are performed to give the magnetic field distributions, toroidal field ripple, in-plane and out-of-plane Lorentz loads. Finally, 3D global and 2D local mechanical analyses are conducted, and the detailed mechanical behavior of the TF coil is illustrated and discussed. Our analyses indicate that the present TF design is reasonable, considering the ITER criteria, and provides valuable insight into the mechanical behavior of the CFETR TF coil system.

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“…The Chinese Fusion Engineering Testing Reactor (CFETR) is the next-generation device for the Chinese magnetic confinement fusion (MCF) program, which aims to bridge the gaps between the fusion experimental reactor ITER and the demonstration reactor DEMO [1][2][3]. The magnet system consists of toroidal field (TF), central solenoid (CS) and poloidal field (PF) coils [4].…”

Section: Introductionmentioning

confidence: 99%

Evaluation of irradiation effects on the microstructure and properties of Ag-sheathed Bi-2212 superconducting round wire for future application in CFETR

Zhu

Qiu

et al. 2020

Supercond. Sci. Technol.

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The Chinese Fusion Engineering Test Reactor (CFETR) is designed to build a fusion engineering Tokamak reactor generating fusion power of 200–1500 MW, and to test the breeding tritium during fusion reaction. This may require a maximum magnetic field up to 15 T in the central solenoid and toroidal field coils. New superconducting materials should be developed for satisfying the next-generation fusion reactors with critical requirements. Recently, Bi2Sr2CaCu2Ox (denoted as Bi-2212) is considered as one of the most promising potential superconductors to be used as the magnets in CFETR, however, they will be subjected to harsh irradiation under operating conditions. The irradiation effects of the high-energy helium ions on the Ag-sheathed Bi-2212 superconducting round wire have been explored for the first time in this work. The microstructure and the critical current at 4.2 K of the superconducting wire before and after irradiation have been carefully investigated. Room-temperature x-ray diffraction (XRD) profiles showed that all the peaks shifted rightward significantly with a broadened (111)Ag peak, indicating that the high-energy He+ irradiation resulted in appreciable defects and strain in the superconducting wire. Meanwhile, the in-situ high-temperature XRD tests showed that the lattice constant and the thermal expansion coefficient were deduced in the irradiated sample to be due to the presence of the generated defects. After irradiation, the grain size of the Ag sheath was refined, and the lattice of Bi-2212 superconductor was distorted obviously, as confirmed by transmission electronic microscopy. The critical current IC at 4.2 K of the superconducting wires in the field of 0–12T determined by the four-probe technique, decreased substantially after irradiation because of the lattice distortion and the consequently induced strain in the Bi-2212 superconductor. This work provides a solid basis for evaluating and understanding the irradiation effects upon the Ag-sheathed Bi-2212 superconducting wire, more promising for future application in CFETR.

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Mechanical performance evaluation of the CFETR central solenoid model coil design

Cited by 15 publications

References 15 publications

Towards Fusion Energy in the Industry 5.0 and Society 5.0 Context: Call for a Global Commission for Urgent Action on Fusion Energy

Towards Fusion Energy in the Industry 5.0 and Society 5.0 Context: Call for a Global Commission for Urgent Action on Fusion Energy

Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors

Evaluation of irradiation effects on the microstructure and properties of Ag-sheathed Bi-2212 superconducting round wire for future application in CFETR

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