European cryogenic material testing program for ITER coils and intercoil structures

Nyilas, A.; Portone, A.; Kiesel, H.

doi:10.1063/1.1472534

Cited by 16 publications

(11 citation statements)

References 3 publications

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“…To improve the FCGR of SUS316LN, two kinds of jackets with coarse and fine grain size were manufactured by changing temperature and time during the solution annealing heat treatment. The chemical compositions of tested materials are summarized in Table II [4], which is acceptable as CS jacket material and SUS316LN with coarse grain indicates better resistance against crack propagation, which mean lower FCGR [3]. However, it was found that the SUS316LN jacket having the fine grain shows lower FCGR than that of SUS316LN jacket with coarse grain and SUS316LN jacket shows faster FCGR than that of expected SUS316LN [4].…”

Section: Selection Filler Materials For Sus316lnmentioning

confidence: 81%

“…The chemical compositions of tested materials are summarized in Table II [4], which is acceptable as CS jacket material and SUS316LN with coarse grain indicates better resistance against crack propagation, which mean lower FCGR [3]. However, it was found that the SUS316LN jacket having the fine grain shows lower FCGR than that of SUS316LN jacket with coarse grain and SUS316LN jacket shows faster FCGR than that of expected SUS316LN [4]. On the other hand, the JK2LB jackets manufactured by two manufactures (Company-A and B) and weld joints show higher resistance against crack propagation, which means lower FCGR than that of SUS316LN.…”

Section: Selection Filler Materials For Sus316lnmentioning

confidence: 99%

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Preparation for the ITER Central Solenoid Conductor Manufacturing

Hamada

Nunoya

Isono

et al. 2012

IEEE Trans. Appl. Supercond.

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The ITER Central Solenoid (CS) conductor is composed of 576 superconducting strands and 288 Cu strands assembled together into a multistage cable and protected by a circle-in-square jacket with the outer dimension of 49 mm 49 mm. In R&D to prepare for the ITER CS conductor manufacturing, mechanical tests of jacket, welding tests and manufacturing of 181-m long dummy conductor have been performed. In this paper, the R&D activities are presented, showing that as a result of this R&D, the CS conductor manufacturing technologies have been preliminary defined to start the procurement of the CS conductor.

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Section: Selection Filler Materials For Sus316lnmentioning

confidence: 81%

Section: Selection Filler Materials For Sus316lnmentioning

confidence: 99%

Preparation for the ITER Central Solenoid Conductor Manufacturing

Hamada

Nunoya

Isono

et al. 2012

IEEE Trans. Appl. Supercond.

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“…where is the allowable stress amplitude for given life cycles, is the fatigue strength at and is the mean stress [6]. S-N experimental data refer to .…”

Section: Fatigue Assessmentmentioning

confidence: 99%

Overview of the ITER Correction Coils Design

Foussat

Libeyre²,

Mitchell³

et al. 2010

IEEE Trans. Appl. Supercond.

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The Correction Coils (CC) of the ITER Tokamak are developed to reduce the range of magnetic error fields created by imperfections in the location and geometry of the other coils used to confine, heat, and shape the plasma. The proposed system consists of three sets of 6 coils each, located at the top (TCC), side (SCC) and bottom (BCC) of the Tokamak device and using a NbTi cable-in-conduit superconducting conductor (CICC). Within each set, the coils are connected in pairs to produce a toroidal field to reduce the most troublesome, lower order, poloidal mode number fields (m = 1 2 3) in order to operate below the locked mode threshold. The conductor is designed to operate up to 6 T. The winding uses pancakes of one-in-hand conductor (quadpancakes for SCC, octopancakes for TCC and BCC), thus avoiding internal joints. The winding-pack is enclosed inside a 20 mm thick stainless steel casing. The coils are supported by rigid connections to the Toroidal Field (TF) coils. The structural design of the CC is mainly driven by the allowable fatigue stress levels in the conductor jacket, in the case material and in the glass-polyimide electrical insulation system. The boundary conditions on the CC are imposed by the TF coils deformation and the electromagnetic interactions with the PF coils system. The thermo-hydraulic and electrical performance of the CICC is also addressed.

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“…However, a detailed study on the performance change of the base tube material after compaction and heat treatment is lacking. In literature mainly experiments on either compacted or annealed specimen can be found [1][2][3][4][5]. Within this paper, tensile tests on compacted and annealed specimen will be presented.…”

Section: Introductionmentioning

confidence: 99%

“…These welds act as weak links that might lead to mechanical failure under applied load. On such welded tube material tensile and fracture toughness experiments were carried out in the past [1][2][3][4][5]. However, a detailed study on the performance change of the base tube material after compaction and heat treatment is lacking.…”

Section: Introductionmentioning

confidence: 99%

Tensile Test Results on Compacted and Annealed 316ln Material

Weiss¹,

Ehrlich²,

Corte³

et al. 2010

AIP Conference Proceedings

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The torodial-field (TF) magnet coils for ITER are made by superconducting cable in conduit conductors (CICC) using 316LN for the conduit. Compaction of the conduit and heat treatment to react the Nb 3 Sn material are one of the main steps during manufacture of this type of conductor. Therefore a systematic investigation was done to examine the influence of compaction and heat treatment on the mechanical behavior of this material. Several 316LN tubes were deformed to smaller radii to obtain different stages of compaction, followed by a heat treatment. From these tubes flat specimen were made by electron-discharge-machining (EDM) for tensile tests. The results are reported and compared to former tests on samples either compacted or heat treated.

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European cryogenic material testing program for ITER coils and intercoil structures

Cited by 16 publications

References 3 publications

Preparation for the ITER Central Solenoid Conductor Manufacturing

Preparation for the ITER Central Solenoid Conductor Manufacturing

Overview of the ITER Correction Coils Design

Tensile Test Results on Compacted and Annealed 316ln Material

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