Theoretical analysis for the mechanical behavior caused by an electromagnetic cycle in ITER $$\hbox {Nb}_{3}\hbox {Sn}$$ Nb 3 Sn cable-in-conduit conductors

Yue, Donghua; Zhang, Xingyi; Zhou, Youhe

doi:10.1007/s10409-017-0748-6

Cited by 11 publications

(3 citation statements)

References 39 publications

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“…For example, short-pitch (STP) cable in conduit conductors (CICC) exhibit excellent characteristics of inhibiting shunt temperature degradation under cyclic electromagnetic loads. This conclusion has been validated by SULTAN’s experiment [ 10 ] and the theoretical prediction given by Lanzhou University [ 11 ]. Therefore, STP-type conductors will also become the first choice for national CFETR high-field coils.…”

Section: Basic Mechanical Problemssupporting

confidence: 57%

Mechanical effects: challenges for high-field superconducting magnets

Zhang¹,

Qin

2022

National Science Review

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Due to its clean products and sufficient raw materials, fusion energy is expected to become one of the main solutions of the energy crisis and ensuring the sustainable development of human society, which is a long-term strategic frontier field. The promise of fusion energy is to constrain the motion of high-temperature plasma by the high magnetic field generated by superconducting magnets, and then achieve controllable thermonuclear fusion. Fusion power is proportional to the fourth power of the magnetic field strength. Thus, future commercial fusion reactors need a higher magnetic field as the basis for sustainable development [1]. In order to verify the scientific and technological feasibility of fusion energy, China, the United States, the European Union, Russia et al. have jointly participated in the construction of the International Thermonuclear Fusion Test Reactor (ITER), which is expected to produce the first plasma discharge by 2025 [2]. Currently, China is leading the world in many fields of fusion energy research. For example, the experimental advanced superconducting Tokamak (EAST) whole-superconducting Tokamak located at the Institute of Plasma Physics in the Chinese Academy of Sciences has achieved a repeatable world record of stable plasma operation at 120 million degrees Celsius for 101 seconds, which provides a solid foundation for ITER and also China's future Independent Building Fusion Reactor (https://www.cas.cn/syky/202105/t20210528_4790357.shtml). Prof. Jiangang Li, an academician of the Chinese Academy of Engineering, participated in and completed the design and construction of EAST plasma facing componments (PFCs) engineering by the support of the national ‘9th five-year plan’ major scientific and technological infrastructure, and presided over the completion of the national ‘11th five-year plan’ major scientific and technological infrastructure—EAST auxiliary heating system project. He also hosted the national ‘13th five-year plan’ major scientific and technological infrastructure—Integrated Research Facility for Critical Systems of fusion reactor comprehensive research facility for fusion technology (CRAFT). Many important scientific and technological problems have been solved and overcome by Prof. Li and his co-workers, which puts China's plasma physics research and fusion engineering technology at the forefront of global engineering.

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Section: Basic Mechanical Problemssupporting

confidence: 57%

Mechanical effects: challenges for high-field superconducting magnets

Zhang¹,

Qin

2022

National Science Review

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“…The short twist pitch (STP) cable pattern has been demonstrated to be successful by the ITER CS and CFETR CSMC conductors [9], no performance degradations was observed on these conductors. The STP cable pattern can effectively prevent the strand movement in cable, hence preventing or at least reducing the number of cracks in the filaments produced by bending strain and Yue's numerical investigation also indicates that STP cable pattern shows higher transverse mechanical strength than that of LTP cable pattern, which is a good support for the test results [25]. Thus, for the HF conductor of the CFETR-TF prototype coil, the STP cable pattern is the first choice.…”

Section: Introductionmentioning

confidence: 62%

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Dai

Wang

et al. 2021

Nucl. Fusion

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The Comprehensive Research Facility for Fusion Technology (CRAFT) project has been launched in 2019, for developing the essential engineering technologies for Chinese Fusion Engineering Testing Reactor (CFETR). Within this project, a full-size toroidal field (TF) coil will be built as the prototype coil for CFETR. Based on design of CFETR magnet system, the TF coil will operate at 95.6 kA in a peak field of 14.5 T. The high-J c Nb3Sn strand is taken into consideration due to the critical current density of ITER-grade Nb3Sn is too low at 14.5 T. Considering that it will be the first time to apply the high-J c Nb3Sn strand in the large-scale cable-in-conduit conductor (CICC) for fusion magnet, a conductor sample made of high-J c Nb3Sn strand with short twist pitch (STP) cable pattern was manufactured in ASIPP and tested in SULTAN facility, to investigate the feasibility. The test campaign focuses on the impact of cyclic electromagnetic (EM) loading and warm-up cool-down (WUCD) to the performance of the conductor, the strain distribution of the conductor before and after EM cycles was measured by inductive method to make a deeper insight of the conductor performance evolution. AC losses tests have also been carried out, providing relevant information for further coil design.

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“…Numerical computations performed with a detailed numerical model specifically developed to analyze the mechanics of CICCs for fusion [9] have also confirmed modifications of the strain distribution due to EM cyclic loading [30]. Further modeling work deals with the computation of T cs of the CS conductors, in which the calculated T cs behavior with cyclic loading shows consistency with the experimental results [31].…”

Section: Assessment Of the Current Sharing Temperaturementioning

confidence: 60%

Performance tests of ITER CS conductor samples from series production

Breschi

Devred

Macioce

et al. 2023

Supercond. Sci. Technol.

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The ITER magnet system is one of the most sophisticated superconducting magnet systems ever designed, with a stored energy of 51 GJ. The coils are wound from Cable-in-Conduit Conductors (CICCs) made of superconducting and copper strands assembled into a multistage rope-type cable, inserted into a conduit of austenitic steel tubes. The ITER Central Solenoid (CS) works in pulsed mode, reaching a peak field of 13 T, thus allowing the induction of a high intensity current in the plasma of the ITER tokamak. This magnet consists of a stack of six modules which include around 125 t of Nb3Sn strands. The production of all CS conductors has been completed and module manufacturing is well underway; throughout the production phase, samples were cut at the extremities of the conductor unit lengths to undergo quality control tests. About 25% of the conductor short samples were tested in current and field at cryogenic conditions at the SULTAN facility in Villigen, Switzerland. This work reports the comparative analysis of the short samples set of test results.

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Theoretical analysis for the mechanical behavior caused by an electromagnetic cycle in ITER $$\hbox {Nb}_{3}\hbox {Sn}$$ Nb 3 Sn cable-in-conduit conductors

Cited by 11 publications

References 39 publications

Mechanical effects: challenges for high-field superconducting magnets

Mechanical effects: challenges for high-field superconducting magnets

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Performance tests of ITER CS conductor samples from series production

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Theoretical analysis for the mechanical behavior caused by an electromagnetic cycle in ITER $$\hbox {Nb}_{3}\hbox {Sn}$$ Nb 3 Sn cable-in-conduit conductors

Cited by 11 publications

References 39 publications

Mechanical effects: challenges for high-field superconducting magnets

Mechanical effects: challenges for high-field superconducting magnets

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J c Nb3Sn strand for fusion reactor

Performance tests of ITER CS conductor samples from series production

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Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor