Test result of full size 40 kA NET/ITER conductor in the FENIX test facility

Bruzzone, P.; Mitchell, N.; Katheder, H.; Salpietro, E.; Chaplin, M.R.; Shen, S.; Slack, D.S.; Rauch, J.; Brehm, Walter; Ceresara, S.; Ricci, M.; Oliva, A. Bonito

doi:10.1109/77.233471

Cited by 16 publications

(6 citation statements)

References 6 publications

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“…An overview of the main events of the ITER conductor development overlaid on the ITER project phases is shown in figure 3. The main events show in particular the consolidation of multiple conductor concepts to that shown in figure 2, in 1993 [29] and the discontinuation of the most exotic jacket materials (for example Incoloy 908 [30]) which had been selected with the objective of optimizing the strand strain in the conductors but in fact drastically complicated the coil manufacturing, in 2003. As will be seen in later sections, several major corrective actions still had to be implemented during manufacturing.…”

Section: Background Ii: Development Of Nb 3 Sn Conductors For the Ite...mentioning

confidence: 99%

The use of Nb₃Sn in fusion: lessons learned from the ITER production including options for management of performance degradation

Mitchell

Breschi

Tronza

2020

Supercond. Sci. Technol.

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The overall 30 year Nb 3 Sn conductor program for ITER provides an unusual opportunity to look at the issues created by the application of novel Nb 3 Sn technology on a large scale. ITER design criteria have evolved to make use of the features of the industrialized material, exploiting advantages as well as managing the disadvantages. There are lessons from the successes and failures to be learned for the future application of very high current Nb 3 Sn strands in fusion and high energy physics. The behaviour of Nb 3 Sn strands in the large compound ITER conductors is still producing surprises after 25 years of development, industrial production and testing, with the Nb 3 Sn strain sensitivity and brittleness producing many more subtle design impacts than originally foreseen. The results now obtained at the end of the ITER production suggest that, as a novelty for Nb 3 Sn, there are options for conditioning the strands in the ITER conductors that can be applied during commissioning and which could reduce the impact of brittleness by as much as one third.

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Section: Background Ii: Development Of Nb 3 Sn Conductors For the Ite...mentioning

confidence: 99%

The use of Nb₃Sn in fusion: lessons learned from the ITER production including options for management of performance degradation

Mitchell

Breschi

Tronza

2020

Supercond. Sci. Technol.

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“…It is interesting to note that already within the NET project development, the solution investigated for the TF conductor was that of a 40 kA-12.5 T rectangular CICC, lacking a central cooling channel [20,136], in many aspects similar to the solution proposed with the EU-AltTF sample. Different prototypes were fabricated and tested and, due the fact that the target VF was kept as high as about 45% [136], the measured pressure drop, ΔP, was considered to be within acceptable levels. In particular, an operating ΔP was computed, of 2 bar for a mass flow rate of 8 g s −1 .…”

Section: The Eu-tfalt Conductor Demonstrationmentioning

confidence: 99%

Cable-in-conduit conductors: lessons from the recent past for future developments with low and high temperature superconductors

Muzzi

Marzi

Zenobio

et al. 2015

Supercond. Sci. Technol.

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We review progress in the design of high field superconducting cable-in-conduit conductors (CICCs) for fusion applications, with special attention to the results of recent key experiments, leading to the state-of-the-art CICC technology: the ITER Toroidal Field and Central Solenoid programs, the EFDA Dipole conductor development program, the NHFML Hybrid Magnet project, the EU-TF Alt conductor demonstration, and the CRPP React & Wind flat cable test. For these projects, the main CICC design driver was the mitigation of Nb 3 Sn conductor performance degradation with electro-magnetic loading cycles. This was achieved by proper choice of cable layout and of conductor geometry, depending on the specific operating conditions and project requirements. In all cases, the necessity to limit cable movements inside the conductor jacket was identified to be of crucial importance. The main aspects of CICC manufacture are also discussed here, at least for what is the experience gained by the authors in both CICC jacketing and cabling processes. Finally, the state of the art of high-temperature superconducting (HTS) cables is discussed: at present, this technology is still in its infancy, but it is highly likely that major technological improvements could eventually lead to a widespread use of HTS CICCs.

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“…The stainless steel conduits were expected to have reduce properties compared to a strand measured on the standard titanium barrel, but better than due to the CTE mismatch between the steel and Nb3Sn strand due to imperfect bond between the conduit and the cable. The subscale experiments carried out at the FENIX facility at LLNL [4], the SULTAN facility at CRPP [5,6] and some subscale experiments [7] suggested that the CICC in the stainless steel experiences significantly less [4,5] degradation than would have been anticipated from about 0.7% mismatch in shrinkage between stainless steel and Nb3Sn strand from the reaction temperature down to the operating temperature. Data from three samples tested at the FENIX facility projected that the effect of the mismatch will be at the level of -0.55% due to some slippage of the cable inside the conduit [4].…”

Section: Iter Model Coil Expectations Before Testsmentioning

confidence: 99%

ITER Model Coil tests overview: Nb3Sn strand properties in cable-in-conduit conductors

Martovetsky

2004

Physica C: Superconductivity

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During the ITER Model Coil Program two large coils and three Insert coils were built and tested. The test campaigns provided very valuable data on the Conductor in Conduit Cable (CICC) properties. The tests showed that the Nb3Sn strands in CICC behave differently than so-called witness strands, which underwent the same heat treatment. The paper describes Volt-temperature characteristics (VTC) and Volt-Ampere characteristics (VAC) measured in the tests, presents comparisons with the witness strands, and interprets the test results.

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Test result of full size 40 kA NET/ITER conductor in the FENIX test facility

Cited by 16 publications

References 6 publications

The use of Nb₃Sn in fusion: lessons learned from the ITER production including options for management of performance degradation

The use of Nb₃Sn in fusion: lessons learned from the ITER production including options for management of performance degradation

Cable-in-conduit conductors: lessons from the recent past for future developments with low and high temperature superconductors

ITER Model Coil tests overview: Nb3Sn strand properties in cable-in-conduit conductors

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Test result of full size 40 kA NET/ITER conductor in the FENIX test facility

Cited by 16 publications

References 6 publications

The use of Nb3Sn in fusion: lessons learned from the ITER production including options for management of performance degradation

The use of Nb3Sn in fusion: lessons learned from the ITER production including options for management of performance degradation

Cable-in-conduit conductors: lessons from the recent past for future developments with low and high temperature superconductors

ITER Model Coil tests overview: Nb3Sn strand properties in cable-in-conduit conductors

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The use of Nb₃Sn in fusion: lessons learned from the ITER production including options for management of performance degradation

The use of Nb₃Sn in fusion: lessons learned from the ITER production including options for management of performance degradation