Qualification tests for ITER TF conductors in SULTAN

Bruzzone, Pierluigi; Stepanov, B.; Wesche, R.

doi:10.1016/j.fusengdes.2008.11.001

Cited by 18 publications

(13 citation statements)

References 16 publications

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“…The main point though is not which small sample values are reached under laboratory conditions, but how a real cable for a large coil performs after all the production and assembly stages, and under the enormous electromagnetic loads. In a Nb 3 Sn cable with steel jacket the thermal compressive strain of the conductor due to different thermal contraction is around 0.5% to 0.6% [9,10]. This reduces the critical current at 12 T, 4.2 K by a factor of more than two [11], whereas for Nb 3 Al the degradation is less than 20% [3,4].…”

Section: Superconductormentioning

confidence: 97%

“…In addition, the strain during magnet loading decreases the performance of Nb 3 Sn further [4]. Practical conductor characteristics far from ideal laboratory values were also revealed during the ITER cable qualification tests where the best critical strand current was by a factor of ∼2.5 below the corresponding value of the best laboratory sample [7,10]. Due to these unpredictable degradations, large safety margins were chosen for ITER.…”

Section: Superconductormentioning

confidence: 99%

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Extrapolation of the W7‐X Magnet System to Reactor Size

Schauer

Wobig

Egorov

et al. 2010

Contrib. Plasma Phys.

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The fusion experiment Wendelstein 7-X (W7-X), presently under construction at the Greifswald branch institute of IPP, shall demonstrate the reactor potential of a HELIAS stellarator. HELIAS reactors with three, four and five periods have been studied at IPP since many years. With a plasma axis induction of 5 T, corresponding to about 10 T maximal induction at the coil, it was shown that such reactors are feasible. Now the possibility is being investigated to increase the conductor induction up to the 12 T -range, corresponding to > 5.5 T at the plasma axis. This improves the stellarator confinement properties but does not change the basic physics with respect to the previously analyzed machines. In particular the 5periodic HELIAS type, HSR5, is considered which evolves from W7-X by linear scaling of the main dimensions by a factor of four.Recent progress in superconductor technology and the extensive development work performed for ITER are taken into account. The latter is particularly relevant since by coincidence the circumferences of the HSR5 and the ITER toroidal field coils are practically the same. For the presented 12 T reactor version, the HSR50a, also the conductor and structural requirements are comparable to the corresponding ITER specifications. Therefore, advantage can be taken of these similarities for the stellarator reactor magnet design.The input was provided by the new code "MODUCO" which was developed for interactive coil layout. It is based on Bézier curve approximations and includes the computation of magnetic surfaces and forces.

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Section: Superconductormentioning

confidence: 97%

Section: Superconductormentioning

confidence: 99%

Extrapolation of the W7‐X Magnet System to Reactor Size

Schauer

Wobig

Egorov

et al. 2010

Contrib. Plasma Phys.

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“…With such a deformation, the area of hysteresis loop was decreased significantly after 1st cycle, which means mechanical heat losses will be fairly reduced after the initial loading. The mechanical heat loss could be calculated using (1) The initial heat loss was evaluated as 103 mJ/m cycle. Then, the loss was appeared as 22 mJ/m cycle at 3rd cycle and was saturated into mJ/m cycle after 20th.…”

Section: A Mechanical Characteristicsmentioning

confidence: 99%

“…T HE 'Option2' was specified, as a recent update of the design of ITER TF conductor, to overcome a known problem of the previous baseline, the performance degradation with respect to cyclic loadings [1]. Keeping the existing design concept as much as possible, the "Option2" specifies only slightly modified dimensions of components with the same cabling scheme as shown in the Table I so that it present the major changes in the void fraction and the twist pitches based on the previous R&D result [2] to improve the performance of the previous baseline which is now called as "Option1".…”

Section: Introductionmentioning

confidence: 99%

Transverse Load Versus Mechanical Characteristics and Inter-Strand Resistances in the Cable of the “Option 2” Specification for ITER TF Conductor

Kim

et al. 2010

IEEE Trans. Appl. Supercond.

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A revised specification of ITER TF conductor was proposed as "Option2" for the baseline design. The cabling pitches of early stages and the void fraction were adjusted in the consequence of previous R&D programs to improve the degradation of performance against cyclic current loadings in the magnetic field. To obtain the characteristics of the developed design, which are related to the effect of the electromagnetic load, the mechanical parameters and the contact resistances between components of cable were investigated employing a specially developed device of cryogenic press in the transverse direction for a short sample of the conductor cable. Through the measurements, the mechanical characteristics against the cyclic loads were discussed, as well as the effect on inter-strand resistances, according to the cable design.

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“…I N the frame of the International Thermonuclear Experimental Reactor (ITER) qualification program, several short toroidal field (TF) conductor samples are being tested for DC characterization in the SULTAN facility at PSI Villigen, CH [1].…”

Section: Introductionmentioning

confidence: 99%

Effects of Mass Flow Rate Imbalance Among Petals During ${\rm T}_{\rm CS}$ Measurements of ITER TF Short Samples in SULTAN

Savoldi

Bellina

Breschi

et al. 2011

IEEE Trans. Appl. Supercond.

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Since year 2009, the joint of the toroidal field (TF) conductor samples tested in the SULTAN facility at PSI Villigen, CH, is solder-filled, so that the helium coolant can only flow axially inside the central channel. The latter is however plugged starting 40-45 mm downstream of the joint. The helium has then to pass from the central channel into the annular cable region over such a short length that the desired homogeneity of the flow distribution among the petals in the high field region is not guaranteed a priori, since central helix and petal wrappings act as azimuthally non-uniform obstacles to the radial flow. In the paper we first present a geometrical model for estimating this interference to the radial flow, and combine it with a CFD (ANSYS-FLUENT) model of the hydraulic effect of the plug, in order to estimate the mass flow rate imbalance among the petals at the beginning of the plug. This is then used as boundary condition by the THELMA code, to parametrically assess the results of a TCS measurement.

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Qualification tests for ITER TF conductors in SULTAN

Cited by 18 publications

References 16 publications

Extrapolation of the W7‐X Magnet System to Reactor Size

Extrapolation of the W7‐X Magnet System to Reactor Size

Transverse Load Versus Mechanical Characteristics and Inter-Strand Resistances in the Cable of the “Option 2” Specification for ITER TF Conductor

Effects of Mass Flow Rate Imbalance Among Petals During ${\rm T}_{\rm CS}$ Measurements of ITER TF Short Samples in SULTAN

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