Progress in Production and Qualification of Stainless Steel Jacket Material for the Conductor of the ITER Central Solenoid

Sgobba, S.; Dalin, J.-M.; Libeyre, P.; Marcinek, Dawid Jarosław; Nyilas, A.

doi:10.1109/tasc.2011.2174547

Cited by 20 publications

(6 citation statements)

References 5 publications

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“…The low temperature mechanical measurements included Fatigue Crack Growth Rate (FCGR) on standardized specimens cut from compacted and aged jacket sections. Figure 41 presents a compilation of available and relevant FCGR data for both 316LN and JK2LB jacket sections [111][112][113][114]. The data of Figure 41 clearly show that JK2LB has a slower FCGR than modified 316LN and confirm that it is a more suitable candidate for CS jacket material.…”

Section: Jacket Materialsmentioning

confidence: 94%

“…This is relatively easy for the welds, where conventional X-ray methods are good enough to achieve the required resolution, but it is far more difficult for the base material, in particular, in the corner areas. At present, the NDE inspection of the CS jacket sections includes a combination of Phase Array Ultrasonic Testing (PAUT) for the material bulk [111,119] and of Eddy current Testing (ET) for the first 2 to 3 mm from the inner bore of the jacket section. The PAUT inspection is well suited for the detection of the most critical defects which are expected to arise from internal longitudinal stresses provoking delamination [120], with a main component parallel to the maximum flow of the material, i.e., in the extrusion and drawing direction.…”

Section: Maximum Flaw Sizes and Jacket Ndementioning

confidence: 99%

“…At present, the NDE inspection of the CS jacket sections for the CS3L module includes a combination of phase array ultrasonic testing (PAUT) for the material bulk [126,134] and of eddy current testing (ET) for the first 2-3 mm from the inner bore of the jacket section. The PAUT inspection is well suited for the detection of the most critical defects which, in pipes of relatively large cross-sectional area and thickness, are expected to arise from internal longitudinal stresses provoking delamination [135], with a main component parallel to the maximum flow of the material, i.e., in the extrusion and drawing direction.…”

Section: Jacket Materialmentioning

confidence: 99%

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Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

170

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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Section: Jacket Materialsmentioning

confidence: 94%

Section: Maximum Flaw Sizes and Jacket Ndementioning

confidence: 99%

Section: Jacket Materialmentioning

confidence: 99%

See 1 more Smart Citation

Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

170

118

View full text Add to dashboard Cite

show abstract

“…The Nb-Ti strands were tested at CERN at 4.2 K and 1.8 K to provide a critical current density Jc expression based on Bottura's fit [9]. A characterization of the strands has been performed and is described in detail in [8]. The values of the fit parameters are provided in Table I.…”

Section: Cable In Conduit Conductor (Cicc)[8]mentioning

confidence: 99%

Development, Integration, and Test of the MACQU Demo Coil Toward MADMAX Quench Analysis

Lorin,

Maksoud,

Allard

et al. 2023

IEEE Trans. Appl. Supercond.

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The MADMAX project aims at detecting axion dark matter in the mass range of 100 µeV. To facilitate axion to photon conversion with detectable rate a superconducting dipole magnet with a large bore is needed. The MADMAX dipole magnet has to generate ~9 T in a 1.35 m aperture over ~1.3 m in length. A key challenge for a magnet made of a cable in-conduit conductor (CICC), operating at 1.8 K with an indirect bath cooling is the quench detection. In order to validate feasibility, a mock-up coil with a quench behavior scalable to MADMAX was designed and produced. The paper gives an overview of the technical details of the MACQU test coil. The conductor, the magnet, the busbar and the supporting and cryogenic systems were designed at CEA. The cable was manufactured in China at the Chang Tong INC from WST Nb-Ti strands, the insertion and compaction was achieved in the ASIPP institute with a copper profile from Aurubis. The winding of the coil and the busbar pre-forming were performed at Bilfinger Noell as well as the assembly of the supporting structure and the thermal shield. The magnet was integrated in the JT60 test station at CEA Saclay and extensively tested. The magnet current reached 80% on the loadline instead of 90% as expected at nominal. The limitation is likely coming from uneven current distribution at the extremity of the magnet at the connection box location. Nevertheless, quench tests were successfully performed at constant currents from 10 kA to 17 kA. They proved that the initial quench velocities are of the order of 1 m/s to 10 m/s, high enough to safely detect a voltage drop in MADMAX and discharge the magnet. In addition, a thermo-hydraulic quench back effect was observed in the MACQU coil cooled by superfluid helium.

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“…A jacket material with a low coefficient of thermal expansion from room temperature to 4 K is desired to increase the preload on the coil winding packs during cool down. The material similar to one used in ITER CS conductor was enhanced for the CFETR CSMC conductor jacket, which was one kind of high-Mn steel [11]- [14]. Meanwhile, the 316LN material was also enhanced for the jacket.…”

Section: Introductionmentioning

confidence: 99%

Manufacturing of Nb₃Sn Sample Conductor for CFETR Central Solenoid Model Coil

Qin¹,

Wu²,

Xiang³

et al. 2017

IEEE Trans. Appl. Supercond.

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China fusion engineering test reactor (CFETR) is a new tokamak device, whose magnet system includes the toroidal field, central solenoid (CS), and poloidal field coils. In order to develop the manufacturing process for the full-size CS coil, the CS model coil (CSMC) project was launched first. The cable-inconduit conductor used for CFETR CSMC refers to ITER CS conductor with the same short twist pitch cable pattern. They have the similar layout. In order to qualify the manufacturing process and performance of conductor, two short sample conductors with two different jacket materials (316LN and high-Mn steel) were manufactured. The conductors were tested at Swiss Plasma Center successfully. In future, the CSMC will be tested at the Institute of Plasma Physics, CAS (ASIPP). In this paper, the manufacturing processes for conductor are described in detail. The strand damage analysis and conductor performance were also discussed.

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Progress in Production and Qualification of Stainless Steel Jacket Material for the Conductor of the ITER Central Solenoid

Cited by 20 publications

References 5 publications

Challenges and status of ITER conductor production

Challenges and status of ITER conductor production

Development, Integration, and Test of the MACQU Demo Coil Toward MADMAX Quench Analysis

Manufacturing of Nb₃Sn Sample Conductor for CFETR Central Solenoid Model Coil

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Progress in Production and Qualification of Stainless Steel Jacket Material for the Conductor of the ITER Central Solenoid

Cited by 20 publications

References 5 publications

Challenges and status of ITER conductor production

Challenges and status of ITER conductor production

Development, Integration, and Test of the MACQU Demo Coil Toward MADMAX Quench Analysis

Manufacturing of Nb3Sn Sample Conductor for CFETR Central Solenoid Model Coil

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Product

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Manufacturing of Nb₃Sn Sample Conductor for CFETR Central Solenoid Model Coil