First ITER CS module test results

Martovetsky, N.; Freudenberg, K.; Hatfield, D.; Rossano, Graham; Reiersen, W.; Khumthong, K.; Langhorn, A.; Norausky, N.; Ortiz, Ed; Piec, Z.; Schaubel, K.M.; Sheeron, Jeffrey; Smith, John P.; Bonifetto, Roberto; Zanino, Roberto; Zappatore, Andrea; Schild, T.; Libeyre, P.; Bessette, D.; Gauthier, Florent; Jong, C.; Ilyin, Y.; Myatt, L.; Cochran, Kristen; Breschi, Marco; Feindt, Wolfgang

doi:10.1016/j.fusengdes.2020.112169

Cited by 12 publications

(3 citation statements)

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“…However, possible mitigation strategies can be put in place: on one hand, the quest for more robust conductor design that are not subject to strong performance degradation under cyclic loadswhich is the direction currently being followed for the conductor development. On the other hand, on the medium term, it is fundamental to test the chosen conductor with short samples as well as long samples and eventually to pursue cold power test of each module to be then assembled in the actual CSwhich is the path followed for the conductors and, more recently, modules of the ITER CS [5].…”

Section: ) Temperature Marginmentioning

confidence: 99%

“…(Corresponding author: andrea.zappatore@polito.it) A. Zappatore, R. Bonifetto and R. Zanino are with the NEMOGroup, Dipartimento Energia, Politecnico di Torino, Torino, 10124, Italy (e-mail: andrea.zappatore@polito.it; roberto.bonifetto@polito.it; roberto.zanino@polito.it). X. Sarasola is with the Ecole Polytechnique Federale e.g., JT-60SA [4] and ITER [5].…”

Section: Introductionunclassified

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Effect of Local Defects on HTS Fusion Magnets Performance

Zappatore

Bonifetto

Zanino

et al. 2022

IEEE Trans. Appl. Supercond.

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Local defects in the manufacturing of High Temperature Superconducting Cable-In-Conduit Conductors (CICC) are known to be present at different stages of the conductor production. The impact of such defects on the performance of one module of the hybrid option of the EU DEMO Central Solenoid is investigated here using the H4C code. For such analysis, the modelling of each strand is needed, since the defect leads to a strong non-uniformity of the current distribution in the conductor cross-section, which in turn causes temperature differences in the cross-section during the propagation of a quench. The analysis allows to assess the level of damage in strand(s) before inducing a quench. In case a quench is initiated, the model is used to follow its propagation to assess the hot-spot temperature. It is also observed that a quench is induced in the Low Temperature Superconducting third layer starting from a quench initiated in the first layer, via inter-layer thermal coupling.

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Section: ) Temperature Marginmentioning

confidence: 99%

Section: Introductionunclassified

Effect of Local Defects on HTS Fusion Magnets Performance

Zappatore

Bonifetto

Zanino

et al. 2022

IEEE Trans. Appl. Supercond.

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“…The first ITER central solenoid (CS) modules recently manufactured are identified, in their cold-tests, to have a lower stiffness than the assumed values for their design [1,2]. The average vertical Young's Modulus, which is a measure of the elasticity, is reduced from the design value of 53 GPa to the measured values (∼32 GPa and ∼34 GPa for CSM1 and CSM2, respectively).…”

Section: Introductionmentioning

confidence: 97%

Exploration of ITER operational space with as-built stiffness of central solenoid modules

Kim,

McIntosh,

Gribov

et al. 2023

Nucl. Fusion

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The as-built stiffness in the ITER central solenoid (CS) modules (CSM1 thorough to CSM4 are currently manufactured) determines the range of vertical compression forces that can be tolerated by the CS modules during ITER operation. Since the as-built stiffness of the CS modules manufactured (~32GPa and ~34GPa for CSM1 and CSM2, respectively and similar for the other modules) has been reduced from the design value (53Gpa), the CS axial (vertical) force criteria have been updated assuming a conservative stiffness (25GPa) with margins for all six CS modules. Initial analysis using the updated CS force criteria has revealed that this reduction affects only the plasma initiation with fully charged CS in the ITER 15MA Baseline DT scenario, resulting in a slight reduction of poloidal magnetic flux, from 117.5Wb to 116.2Wb at initial CS magnetization. Therefore, the 15MA Baseline scenario has been re-developed with an updated plasma start-up, and then the entire evolution of the CS and poloidal field (PF) coil parameters has been validated against all the coil currents, fields and forces criteria. To explore potential risks and opportunities for further optimization of scenarios, the equilibrium operational space (the plasma internal inductance versus the poloidal magnetic flux produced by the coils) at flat-top burn has been analysed using the CORSICA and DINA codes. The three major ITER reference DT operation scenarios, 15MA Q = 10 Baseline, 12.5MA Q > 5 Hybrid and 10MA Q ~ 5 Steady-State, satisfy all the coil criteria including the CS force updated reflecting the as-built stiffness. The evolution of the plasma discharge parameters within the equilibrium operational spaces provided a guidance for potential optimization with margins.

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