Optimization of CFETR CSMC cabling based on numerical modeling and experiments

Qin, Jinggang; Dai, Chao; Liu, Bo; Wang, Yu; Liu, Fang; Liao, Guojun; Xue, Tianjun; Wei, Zhourong; Nijhuis, A.; Zhou, Chao; Devred, A.

doi:10.1088/0953-2048/28/12/125008

Cited by 32 publications

(21 citation statements)

References 31 publications

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“…From the present research, the conductor with short-twist-pitch (STP) design has no degradation, but remarkably improves performance with EM loading and thermal cycles [11,12]. From the experimental and mechanical computations, the results show that the STP conductor has high cable stiffness, avoiding strand movement and fatigue behavior but with high indentation (strand deformation) during cable and conductor compaction [13,14]. Research has been carried out on the performance of strand with indentation, showing that indentation of less than some value (e.g.…”

Section: Introductionmentioning

confidence: 93%

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New design of cable-in-conduit conductor for application in future fusion reactors

Qin

Wang

et al. 2017

Supercond. Sci. Technol.

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The China Fusion Engineering Test Reactor (CFETR) is a new tokamak device whose magnet system includes toroidal field, central solenoid (CS) and poloidal field coils. The main goal is to build a fusion engineering tokamak reactor with about 1 GW fusion power and self-sufficiency by blanket. In order to reach this high performance, the magnet field target is 15 T. However, the huge electromagnetic load caused by high field and current is a threat for conductor degradation under cycling. The conductor with a short-twist-pitch (STP) design has large stiffness, which enables a significant performance improvement in view of load and thermal cycling. But the conductor with STP design has a remarkable disadvantage: it can easily cause severe strand indentation during cabling. The indentation can reduce the strand performance, especially under high load cycling. In order to overcome this disadvantage, a new design is proposed. The main characteristic of this new design is an updated layout in the triplet. The triplet is made of two Nb 3 Sn strands and one soft copper strand. The twist pitch of the two Nb 3 Sn strands is large and cabled first. The copper strand is then wound around the two superconducting strands (CWS) with a shorter twist pitch. The following cable stages layout and twist pitches are similar to the ITER CS conductor with STP design. One short conductor sample with a similar scale to the ITER CS was manufactured and tested with the Twente Cable Press to investigate the mechanical properties, AC loss and internal inspection by destructive examination. The results are compared to the STP conductor (ITER CS and CFETR CSMC) tests. The results show that the new conductor design has similar stiffness, but much lower strand indentation than the STP design. The new design shows potential for application in future fusion reactors.

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Section: Introductionmentioning

confidence: 93%

“…The assessment of indentation on strand was performed based on destructive examination. Generally, the final cable was cut into a short sample (at least one pitch long, here a 1.2 m length was taken) and the indentation depth was investigated by means of a micrometer [14,24].…”

Section: Destructive Examinationmentioning

confidence: 99%

New design of cable-in-conduit conductor for application in future fusion reactors

Qin

Wang

et al. 2017

Supercond. Sci. Technol.

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“…The introduction of the copper strand has been found to greatly reduce the axial stiffness of the strand, and the contact deformation between the strands has been found to have a great influence on the stiffness of the strand. The theoretical calculation results have appeared to be in good agreement with the experiments [13,14]. Yue et al have conducted a systematic mechanical analysis of the CICC in the design, preparation, and operation stage [15][16][17][18].…”

Section: Introductionmentioning

confidence: 53%

The Mechanical Behavior of the Cable-in-Conduit Conductor in the ITER Project

Yue¹,

Zhang²,

Zhou³

2019

Nuclear Fusion - One Noble Goal and a Variety of Scientific and Technological Challenges

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Cable-in-conduit conductor (CICC) has wide applications, and this structure is often served to undergo heat force-electromagnetic coupled field in practical utilization, especially in the magnetic confinement fusion (e.g., Tokamak). The mechanical behavior in CICC is of relevance to understanding the mechanical response and cannot be ignored for assessing the safety of these superconducting structures. In this chapter, several mechanical models were established to analyze the mechanical behavior of the CICC in Tokamak device, and the key mechanical problems such as the equivalent mechanical parameters of the superconducting cable, the untwisting behavior in the process of insertion, the buckling behavior of the superconducting wire under the action of the thermo-electromagnetic static load, and the Tcs (current sharing temperature) degradation under the thermo-electromagnetic cyclic loads are studied. Finally, we summarize the existing problems and the future research points on the basis of the previous research results, which will help the related researchers to figure out the mechanical behavior of CICC more easily.

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“…developed the cabling technology and measured the strand deformation, as well as critical current (I c ) degradation in the cabling process. Subsequently, a prototype CICC manufacture and visual inspection of cable damage with deformation has been performed, which ensures the feasibility of manufacturing technology for Nb 3 Sn CICC [10], [11]. The detailed structure characteristics of the Nb 3 Sn CICC are shown in Table I.…”

Section: A Nb 3 Sn Cable-in-conduit Conductormentioning

confidence: 99%

“…The cable jacket is cut in half with a separation so that the applied load force (F y ) can compress the bundle freely. The virgin state of the cable is maintained by the locked void-fraction method [10]. The stress inside the cable is calculated for two different configurations by using FEM with a computer code called ELCUT: First, for the case of the cable in the cryogenic press, and second, for the real Lorentz force distribution in the ITER magnet.…”

Section: B Experiments Proceduresmentioning

confidence: 99%

Mechanical and Electrical Properties of a CFETR CSMC Conductor Under Transverse Mechanical Loadings

Shi

Qin

Wang

et al. 2018

IEEE Trans. Appl. Supercond.

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The central solenoid model coil (CSMC) project of the China Fusion Engineering Test Reactor was launched in 2014 to verify the technological feasibility of a large-scale superconducting magnet at the Institute of Plasma and Physics Chinese Academy of Sciences. The short twist pitch design recommended by CEA is chosen for the CSMC Nb 3 Sn cable-in-conduit conductors. In order to better understand the evolution of transport properties and coupling losses related to the effect of electromagnetic load cycles, the mechanical and electrical properties were measured and investigated employing a special cryogenic press facility for the transverse mechanical loadings. The results show that the transverse compression (d y) versus applied load force (F y) is different from first to subsequent loading cycles. This mechanical behavior can be interpreted by the combination of strands bending between the crossovers and strands deformation at the crossovers. The fitting relations of d y versus F y are also presented. The evolution of interstrand contact resistance (R c) in the cabling stages with cyclic history and pressure effects are discussed. In addition, a fitting relation of R c versus F y is presented based on a combination of strand's microsliding and copper matrix resistivity. A clear correlation between intrapetal resistance R c and coupling loss is also found.

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Optimization of CFETR CSMC cabling based on numerical modeling and experiments

Cited by 32 publications

References 31 publications

New design of cable-in-conduit conductor for application in future fusion reactors

New design of cable-in-conduit conductor for application in future fusion reactors

The Mechanical Behavior of the Cable-in-Conduit Conductor in the ITER Project

Mechanical and Electrical Properties of a CFETR CSMC Conductor Under Transverse Mechanical Loadings

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