Electromagnetic Analysis of the Voltage-Temperature Characteristics of the ITER TF Conductor Samples

Breschi, Marco; Ribani, Pier Luigi; Bellina, F.

doi:10.1109/tasc.2009.2018120

Cited by 18 publications

(14 citation statements)

References 7 publications

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“…Six virtual voltage taps on the jacket were considered in simulations corresponding to the real instrumentation of the SULTAN facility. The main features of the experimental results are correctly reproduced by the model, as shown in [13] by direct comparison with experimental results. The computed jacket and cable voltages were therefore treated with the same procedure developed to analyze the SULTAN tests, averaging over the last 50 s of each step as indicated in the standard procedure.…”

Section: B Error Due To the Difference Between Cable And Jacket Voltsupporting

confidence: 60%

Error Estimation in the $T_{cs}$ Measurement of TF Conductors in the SULTAN Facility

Breschi

Ribani

Bessette

et al. 2012

IEEE Trans. Appl. Supercond.

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The main parameter measured in the tests of the TF conductors for the ITER machine is the current sharing temperature . In the voltmetric assessment of , the voltages are measured on the conductor jacket, due to the technical difficulties to introduce voltage taps inside the stainless steel conduit. The average voltages measured on the jacket do not exactly correspond to those that arise along the single strands, as shown by the presence of early voltages arising during the current ramp up, when the cable is still in the superconducting phase. It is therefore not trivial to evaluate the difference between the cable and jacket voltages, that gives rise to an experimental error in the measurement of . This paper reports the results of a vast simulation campaign performed with a detailed electromagnetic model of the Cable in Conduit Conductor, in which the origin and the extent of these differences have been investigated, giving an estimate for the experimental error. The impact on measurements of other sources of error such as the signal/noise ratio and the error in the temperature measurements is also reported.Index Terms-Cable in conduit conductors, error estimation, measurement.

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Section: B Error Due To the Difference Between Cable And Jacket Voltsupporting

confidence: 60%

Error Estimation in the $T_{cs}$ Measurement of TF Conductors in the SULTAN Facility

Breschi

Ribani

Bessette

et al. 2012

IEEE Trans. Appl. Supercond.

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“…In 2007 and 2008, ITER IO funded several contracts at CRPP to improve SULTAN sample preparation and address the above issues. The final procedure, agreed with all six domestic agencies involved in conductor production, and which is used for qualification and production samples, includes [47]  2 sets of crimping rings at both ends of the sample (to prevent cable/jacket slippage; see Figure 15a) [48],  solder-filled joints for both the bottom joint and the upper terminations (to ensure good current uniformity among cable strands; see Figure 15b) [49][50],  crown arrays of 6 voltage taps and 4 temperature sensors mounted on the conductor jacket and on both sides of the High Field Zone (which have been shown by analyses to best approximate average cable properties; see Figure 15c) [51]. The results of these improvements are clearly illustrated in Figures 16(a) and (b) which display the results of T Cs runs carried out on 2 sets of full-size, Nb 3 Sn conductor samples for ITER: one set tested before (16a) [52] and one set tested after (16b) the final preparation procedure was implemented.…”

Section: Sultan Sample Issuesmentioning

confidence: 99%

Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

177

118

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Taking the relay of the Large Hadron Collider (LHC) at CERN, ITER has become the largest project in applied superconductivity. In addition to its technical complexity, ITER is also a management challenge as it relies on an unprecedented collaboration of 7 partners, representing more than half of the world population, who provide 90% of the components as in-kind contributions. The ITER magnet system has a stored energy of 51 GJ and involves 6 of the ITER partners. The coils are wound from Cable-In-Conduit Conductors (CICCs) made up of superconducting and copper strands assembled into a fully transposed, rope-type cable, inserted into a conduit of butt-welded austenitic steel tubes. The conductors for the Toroidal Field (TF) and Central Solenoid (CS) coils require about 500 tons of Nb 3 Sn strands while the Poloidal Field (PF) and Correction Coil (CC) and busbar conductors need around 250 tons of Nb-Ti strands. The required amount of Nb 3 Sn strands far exceeds pre-existing industrial capacity and has called for a significant worldwide production scale up. The TF conductors are the first ITER components to be mass produced and are more than 50% complete. During its life time, the CS coil will have to sustain several tens of thousands of electromagnetic (EM) cycles to high current and field conditions, way beyond anything a large Nb 3 Sn coil has ever experienced. Following a comprehensive R&D program, a technical solution has been found for the CS conductor, which ensures stable performance versus EM and thermal cycling. Productions of PF, CC and busbar conductors are also underway. After an introduction to the ITER project and magnet system, we describe the ITER conductor procurements and the Quality Assurance/Quality Control programs that have been implemented to ensure production uniformity across numerous suppliers. Then, we provide examples of technical challenges that have been encountered and we present a status of ITER conductor production worldwide.

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“…Because of the space restrictions in the SULTAN magnet system, the bottom joint is only 565 mm from the center of the HFZ. As a result, a set of investigations has been conducted on the effect of the joint technology on the sample performance, both with experiments [38][39][40] and with independent numerical simulations [16,17,41,42]. ITER's SULTAN Working Group (SWG) has settled on the 'solder filled' joint technology, introduced in [14] and first adopted for the ITER conductors of the last generation by the US-DA [9].…”

Section: Sample Preparation and Instrumentationmentioning

confidence: 99%

Results of the TF conductor performance qualification samples for the ITER project

Breschi

Devred

Casali

et al. 2012

Supercond. Sci. Technol.

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The performance of the toroidal field (TF) magnet conductors for the ITER machine are qualified by a short full-size sample (4 m) current sharing temperature (Tcs) test in the SULTAN facility at CRPP in Villigen, Switzerland, using the operating current of 68 kA and the design peak field of 11.8 T. Several samples, including at least one from each of the six ITER Domestic Agencies participating in TF conductor fabrication (China, European Union, Japan, Russia, South Korea and the United States), have been qualified by the ITER Organization after achieving Tcs values of 6.0–6.9 K, after 700–1000 electromagnetic cycles. These Tcs values exceed the ITER specification and enabled the industrial production of these long-lead items for the ITER tokamak to begin in each Domestic Agency. Some of these samples did not pass the qualification test. In this paper, we summarize the performance of the qualified samples, analyze the effect of strand performance on conductor performance, and discuss the details of the test results.

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Electromagnetic Analysis of the Voltage-Temperature Characteristics of the ITER TF Conductor Samples

Cited by 18 publications

References 7 publications

Error Estimation in the $T_{cs}$ Measurement of TF Conductors in the SULTAN Facility

Error Estimation in the $T_{cs}$ Measurement of TF Conductors in the SULTAN Facility

Challenges and status of ITER conductor production

Results of the TF conductor performance qualification samples for the ITER project

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