Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

Liu, Xiaogang; Qiu, Liping; Li, Jun; Wang, Zhaoliang; Ren, Yong; Wang, Xianwei; Li, Guoqiang; Gao, Xiang; Bi, Yuehong

doi:10.1088/1741-4326/57/1/016037

Cited by 6 publications

(3 citation statements)

References 29 publications

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“…To create and maintain the low temperature operating conditions for the superconducting magnet system, meanwhile for the cryopumps, thermal shields and other small users, the heat load estimation and conceptual design of the CFETR cryogenic system have been conducted [36]. The heat loads of the CFETR cryogenic system are estimated based on a baseline scenario: a fusion power of 200 MW with a plasma current of 10 MA and burn duty cycle (defined as the ratio of plasma burn time to repetition time) of 50%.…”

Section: Cryogenic Systemmentioning

confidence: 99%

Overview of the present progress and activities on the CFETR

et al. 2017

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The China Fusion Engineering Test Reactor (CFETR) is the next device in the roadmap for the realization of fusion energy in China, which aims to bridge the gaps between the fusion experimental reactor ITER and the demonstration reactor (DEMO). CFETR will be operated in two phases. Steady-state operation and self-sufficiency will be the two key issues for Phase I with a modest fusion power of up to 200 MW. Phase II aims for DEMO validation with a fusion power over 1 GW. Advanced H-mode physics, high magnetic fields up to 7 T, high frequency electron cyclotron resonance heating and lower hybrid current drive together with off-axis negative-ion neutral beam injection will be developed for achieving steady-state advanced operation. The recent detailed design, research and development (R&D) activities including integrated modeling of operation scenarios, high field magnet, material, tritium plant, remote handling and future plans are introduced in this paper.

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Section: Cryogenic Systemmentioning

confidence: 99%

Overview of the present progress and activities on the CFETR

et al. 2017

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“…The corresponding current of a NbTi strand in PF cables is roughly 50 to 70 A, and the current sharing temperature of the PF cables is 6 to 7 K [10]. The design requirement of CFETR magnet system also have six ITER-like PF coils operating with maximum currents of 50 kA at 4.2 K, which generates a peak magnetic field of about 6 T as well [11]. If using MgB 2 wire instead of the NbTi wire, several aspects are required to be evaluated: firstly, the price (US dollar/kA•m) of MgB 2 is not yet competitive with that of NbTi at 4.2 K, however, it is expected that the supply of large quantities of conductor will lead to optimization and cost reduction.…”

Section: Introductionmentioning

confidence: 99%

DC performance and AC loss of sub-size MgB₂ CICC conductor for fusion magnet application

Gao¹,

He²,

Ma³

et al. 2022

Nucl. Fusion

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Given the low price and relatively high transition temperature (39 K) of MgB2 conductor, MgB2-based superconductors are a potential candidate for the lower field fusion coils, such as Poloidal Field (PF) coils, Correction Coils (CC) and Feeders. However, to date, the application of MgB2 is limited to demonstrators in a low magnetic field of up to 5 T and at temperatures of up to 10 to 20 K, relying on cryogen-free, helium gas or liquid hydrogen cooling, which significantly reduce the cost of cryogenic systems. To demonstrate the feasibility and performance verification of large size MgB2 PF conductors based on ITER and CFETR requirements, a 4th-stage subsize MgB2 Cable-In-Conduit Conductor (CICC) cable sample is made at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). The CICC contains 96 in-situ MgB2 superconducting wires, manufactured by Western Superconducting Technology Ltd. (WST) and 48 copper wires. The critical current of the sub-size cables and MgB2 witness wires are examined with different background magnetic fields at 4.2 K. In addition, the AC loss is measured utilizing magnetization and calorimetric methods. To further clarify the influence of electromagnetic force on the AC loss performance, the cable sample is pressed transversely at room temperature and then inserted into a dipole magnet for AC loss measurement at 4.2 K. The critical current at 4.2 K of the subsize MgB2 CICC cable shows 20% degradation compared to the witness wires at 2 T background magnetic field. However, no further critical current degradation is visible during ramping up and down the magnetic field. The coupling loss time constant for 1 T background magnetic field amounts to 480 ms. No significant effect of the applied transverse stress on the coupling loss is observed between 0 and 10 MPa.

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“…After ITER, construction of a demonstration fusion reactor (DEMO) will be a necessary next step to develop the scientific and technological viability of a commercial fusion power plant. Conceptual designs have been conducted for EU-DEMO [1,2], JA-DEMO [3], K-DEMO [4][5][6] and CFETR [7][8][9], etc. CFETR aims to initially demonstrate fusion energy production of 200 MW and eventually reach a DEMO relevant power of 1 GW.…”

Section: Introductionmentioning

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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Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

Cited by 6 publications

References 29 publications

Overview of the present progress and activities on the CFETR

Overview of the present progress and activities on the CFETR

DC performance and AC loss of sub-size MgB₂ CICC conductor for fusion magnet application

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

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Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

Cited by 6 publications

References 29 publications

Overview of the present progress and activities on the CFETR

Overview of the present progress and activities on the CFETR

DC performance and AC loss of sub-size MgB2 CICC conductor for fusion magnet application

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

Contact Info

Product

Resources

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DC performance and AC loss of sub-size MgB₂ CICC conductor for fusion magnet application