Status of Conductor Qualification for the ITER Central Solenoid

Devred, A.; Bessette, D.; Bruzzone, Pierluigi; Hamada, K.; Isono, T.; Martovetsky, N.; Mitchell, N.; Nunoya, Y.; Okuno, K.; Pong, Ian; Reiersen, W.; Rey, C.M.; Stepanov, B.; Takahashi, Yoshikazu; Vostner, A.

doi:10.1109/tasc.2013.2245391

Cited by 56 publications

(90 citation statements)

References 17 publications

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“…The Cu strands in the cable have already been determined to have an effect [6,7,35]. But, current distribution inside CICC does not seem to be easily controlled and can be affected by external factors making it difficult to predict as well.…”

Section: Resulting Internal Self-field Of Cablementioning

confidence: 99%

“…The main problem with the magnet was that the Nb 3 Sn based Cable-In-Conduit Conductor (CICC) that makes up each module was not performing to requirements during early tests. Specifically, CICC samples subjected to high background field were showing lower and lower current sharing temperature (T cs ) without stabilization, with repeated electromagnetic (EM) loading from current cycling [4][5][6][7]. The minimum T cs was set at 5.2 K and this requirement was being breached, sometimes after several thousand current cycles, with the original CICC design.…”

Section: Introductionmentioning

confidence: 99%

“…Premature failure of the design, however, prompted further investigation into improving performance with modified CICC designs. The ITER International Organisation (IO) which is responsible for the design of ITER led a study that uncovered a solution to the problem in the form of a design change to the CICC cable, which brought about a return to shorter sub-cable twist pitches [6,7,12,13]. Additional investigation with different CICC samples confirmed the improved performance from the changed design [6], [13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

“…Relaxation in the intrinsic strain of a Nb 3 Sn strand sample is currently the only identified mechanism that improves strand I c , and improvement of I c leads to improvement of T cs [6,7,13,16,27]. It follows then that the initial improvement in T cs seen in STP cable CICC is due to the intrinsic strain in the strands being relaxed, initiated by the internal EM forces within the cable.…”

Section: Introduction To Iter Cs Conductor Design and Performancementioning

confidence: 99%

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Comparisons of internal self-field magnetic flux densities between recent Nb₃Sn fusion magnet CICC cable designs

Kwon¹

2016

Progress in Superconductivity and Cryogenics

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The Cable-In-Conduit-Conductor (CICC) for the ITER tokamak Central Solenoid (CS) has undergone design change since the first prototype conductor sample was tested in 2010. After tests showed that the performance of initial conductor samples degraded rapidly without stabilization, an alternate design with shorter sub-cable twist pitches was tested and discovered to satisfy performance requirements, namely that the minimum current sharing temperature (T cs ) remained above a given limit under DC bias. With consistent successful performance of ITER CS conductor CICC samples using the alternate design, an attempt is made here to revisit the internal electromagnetic properties of the CICC cable design to identify any correlation with conductor performance. Results of this study suggest that there may be a simple link between the Nb 3 Sn CICC internal self-field and its T cs performance. The study also suggests that an optimization process should exist that can further improve the performance of Nb 3 Sn based CICC.

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Section: Resulting Internal Self-field Of Cablementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introduction To Iter Cs Conductor Design and Performancementioning

confidence: 99%

See 2 more Smart Citations

Comparisons of internal self-field magnetic flux densities between recent Nb₃Sn fusion magnet CICC cable designs

Kwon¹

2016

Progress in Superconductivity and Cryogenics

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“…Degradation of critical currents of superconductors by electromagnetic forces was observed in the Nb 3 Sn conductors for the ITER-TF and CS coils [1]. Degradation should be more serious in the higher field magnets.…”

Section: Introductionmentioning

confidence: 92%

Plan for Testing High-Current Superconductors for Fusion Reactors with A 15T Test Facility

Imagawa

Obana

Takada

et al. 2015

Plasma and Fusion Research

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Fusion power plants need larger scale and higher field superconducting magnets than the ITER magnets. Therefore, higher current superconductors with high strength against strong electromagnetic forces are needed. In order to examine the superconducting properties of such large conductors in real conditions, we are preparing a new test facility that is equipped with a solenoid coil of the highest field of 13 T with the bore of 0.7 m, a pair of temperature-variable current leads, and a vacuum chamber for conductor samples. The highest field can be increased to 15 T by installing an additional coil with the cold bore of 0.6 m. Since the inlet temperature of the samples can be varied from 4.4 K to 50 K, it is possible to examine properties of advanced conductors at actual operating temperatures including high-temperature superconductors. We propose coil-shaped conductor samples instead of straight samples in order to apply electromagnetic hoop forces on the conductors to realize the real condition. A reference design of a sample for a cable-in-conduit conductor is provided.

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Extraction on the Contact Forces Among the Opaque and Non-photoelastic Particles Under Electromagnetic Force

Jiao

Liu

Zhou

et al. 2021

Acta Mech. Solida Sin.

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Status of Conductor Qualification for the ITER Central Solenoid

Cited by 56 publications

References 17 publications

Comparisons of internal self-field magnetic flux densities between recent Nb₃Sn fusion magnet CICC cable designs

Comparisons of internal self-field magnetic flux densities between recent Nb₃Sn fusion magnet CICC cable designs

Plan for Testing High-Current Superconductors for Fusion Reactors with A 15T Test Facility

Extraction on the Contact Forces Among the Opaque and Non-photoelastic Particles Under Electromagnetic Force

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Status of Conductor Qualification for the ITER Central Solenoid

Cited by 56 publications

References 17 publications

Comparisons of internal self-field magnetic flux densities between recent Nb3Sn fusion magnet CICC cable designs

Comparisons of internal self-field magnetic flux densities between recent Nb3Sn fusion magnet CICC cable designs

Plan for Testing High-Current Superconductors for Fusion Reactors with A 15T Test Facility

Extraction on the Contact Forces Among the Opaque and Non-photoelastic Particles Under Electromagnetic Force

Contact Info

Product

Resources

About

Comparisons of internal self-field magnetic flux densities between recent Nb₃Sn fusion magnet CICC cable designs

Comparisons of internal self-field magnetic flux densities between recent Nb₃Sn fusion magnet CICC cable designs