A thermo-hydraulic analysis of the superconducting proposal for the TF magnet system of FAST

Polli, Gian Mario; Corte, A. della; Zenobio, A. Di; Muzzi, L.; Reccia, L.; Turtù, S.; Brolatti, G.; Crisanti, F.; Cucchiaro, A.; Pizzuto, A.; Villari, R.

doi:10.1016/j.fusengdes.2011.01.107

Cited by 4 publications

(6 citation statements)

References 10 publications

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“…Currently, FAST magnetic system is designed with 18 TF (Toroidal Field), 6 CS (Central Solenoid) and 6 PF (Poloidal Field) resistive coils, cooled by helium gas flow at 30 K. A feasibility study to verify whether a superconductive (SC) solution for the whole magnetic system would be possible or not, avoiding any major modifications to the machine geometry or scenarios, is currently under study at ENEA. In [3] the authors carried out a thermo-hydraulic analysis of the TF superconducting to verify the feasibility of the SC design. However, the contribution to the heat load coming from the casing to the winding pack (WP) was not modeled in that paper.…”

Section: F Ast (Fusion Advanced Studies Torus) Is Thementioning

confidence: 99%

“…The preliminary design of the SC proposal of the TF has already been discussed in [3] and [6], where the interested reader is referred to for a general description of the system. Fig.…”

Section: Tf Magnet Modelmentioning

confidence: 99%

“…The data of the heat flux, coming from the previous analysis, pertaining to each turn, constitutes the missing ingredient of the thermal-hydraulic analysis carried out in [3]. In particular, these data enter into definition of the power load acting of the steel conduit.…”

Section: B 1d Model Analysismentioning

confidence: 99%

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2D Thermal Analysis of the Superconducting Proposal for the TF Magnets of FAST

Polli

Roccella

Corte

et al. 2012

IEEE Trans. Appl. Supercond.

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The design of FAST (Fusion Advanced Studies Torus), the Italian proposal of a Satellite Facility to ITER, is currently under review in order to verify the feasibility of a superconducting version of its magnet system. In a previous study, the 1D analysis of the thermal-hydraulics of the TF cable in conduit conductors (CICCs) have been investigated with respect to one of the most critical operating scenarios (the H-mode reference scenario). In that case the heat coming from the casing to the winding pack due to the nuclear heat from the plasma has not been modeled, nonetheless, based on the experience on other superconducting tokamak machines, the necessity for a proper shield and case cooling system has been recognized. In the present paper the effect of the heat coming from the casing is quantified through a 2D analysis of the TF cross section. The contribution of the casing is further employed as an input for a successive 1D thermal-hydraulic analysis of the CICCs.

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Section: F Ast (Fusion Advanced Studies Torus) Is Thementioning

confidence: 99%

“…The preliminary design of the SC proposal of the TF has already been discussed in [3] and [6], where the interested reader is referred to for a general description of the system. Fig.…”

Section: Tf Magnet Modelmentioning

confidence: 99%

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2D Thermal Analysis of the Superconducting Proposal for the TF Magnets of FAST

Polli

Roccella

Corte

et al. 2012

IEEE Trans. Appl. Supercond.

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“…With this design, the conductor temperature marfin is around 0.9 K for a nuclear heating of about 5 mWlcm . Then superconductor coils could be introduced in the current machine load assembly design without any major modifications [19].…”

Section: Toroidal Field Coil Systemmentioning

confidence: 99%

Advances in the FAST program

Cucchiaro

Brolatti

Calabrò

et al. 2011

2011 IEEE/NPSS 24th Symposium on Fusion Engineering

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FAST (Fusion Advanced Studies Torus) is a p ro p osal for a Satellite Facility which can contribute the ra p id ex p loitation of ITER and p re p are ITER and DEMO regimes of o p eration, as well as ex p loiting innovative DEMO technology. FAST o p erates with high p erformance H-Mode (BT up to 8.5 T; Ip up to 8 MA) as well as Advanced Tokamak o p eration (Ip=3 MA), and full non inductive current scenario (Ip=2 MA) [1). The p roject is based on a dominant 30 MW of ICRH, 6 MW of LH and 4 MW of ECRH. Helium gas at 30K is used for cooling the resistive co pp er magnets, which dimensions have been determined to limit the coil tem p erature at the end of the longest p ulses ( p ulse length u p to 170 s). The p eak current density in the reference H-mode is about 45 MA/m 2 • The Finite Element Method (FEM) has been em p loyed to analyse the stresses of the load assembly structure (2) using the ANSYS code. Due to the full structural coo p eration, the Toroidal Field Coils, Central Solenoid and mechanical structure, have been modelled as a whole, using mechanical and thermal smeared p ro p erties. Structural analyses were p erformed at the most significant times of the o p erating scenario. The FW consists of a bundle of coaxial tubes armoured with 4

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“…It has been conceived as a compact ( 1.82 m) machine working at high field ( up to 8.5 T) and high plasma current ( up to 8 MA). Currently, FAST magnetic system is designed with 18 TF (Toroidal Field), 6 CS (Central Solenoid) and 6 PF (Poloidal Field) resistive coils, cooled by helium gas flow at 30 K. A feasibility study to verify whether a superconducting (SC) solution for the whole magnetic system would be possible or not, Manuscript avoiding any major modifications to the machine geometry or scenarios, has been discussed in [3], and with respect to the TF magnet system in [4] and [5]. This paper focuses on the proposed superconducting solution for the CS magnet in order to assess its feasibility, keeping the reference H-mode scenario, foreseen for the resistive configuration of the machine, as a constraint, and regardless the performance degradation of the conductor.…”

Section: Introductionmentioning

confidence: 99%

1-D Electromagnetic and Thermal-Hydraulic Analysis of the Superconducting Proposal for the CS Magnets of FAST

Polli

Muzzi

Pompeo

et al. 2012

IEEE Trans. Appl. Supercond.

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FAST (Fusion Advanced Studies Torus), the Italian\ud proposal of a Satellite Facility to ITER, has been the object of an\ud intense re-design activity aimed at verifying the feasibility of a superconducting solution for its magnet system. One of the most difficult and critical obstacles is represented by the central solenoid\ud (CS) magnet, due to the rapid variation of the current and magnetic field (up to 40 T/s) foreseen so far in the reference scenario.\ud The associated losses induced in the CS magnets should be dissipated by the flow of helium that cools the conductors. Nonethe-\ud less, even the losses depend on the conductor design, therefore,\ud not only the thermal-hydraulics of the Cable-in-Conduit Conduc-\ud tors (CICCs) but also the strand properties, should be considered\ud to identify the best design capable to sustain the transient in the\ud CS magnets, keeping the scenario originally foreseen for the resistive configuration of the machine unaltered. The present paper discusses the electromagnetic and thermal-hydraulic behavior of the\ud CICC design envisaged for the FAST CS magnet in the H-mode\ud scenario, and identifies the possible strategies to make a superconducting solution sustainable

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A thermo-hydraulic analysis of the superconducting proposal for the TF magnet system of FAST

Cited by 4 publications

References 10 publications

2D Thermal Analysis of the Superconducting Proposal for the TF Magnets of FAST

2D Thermal Analysis of the Superconducting Proposal for the TF Magnets of FAST

Advances in the FAST program

1-D Electromagnetic and Thermal-Hydraulic Analysis of the Superconducting Proposal for the CS Magnets of FAST

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