Development of a Two-Dimensional Simplified Tool for the Analysis of the Cooling of the ITER TF Winding Pack

Pietro Alessandro Di Maio, Ruggero Forte, Alfredo Portone, Francesca Cau

Research output: Contribution to journalArticle

Abstract

The cooling of the ITER toroidal field (TF) coils winding pack is guaranteed by the circulation of supercritical helium (He) in seven hydraulic circuits corresponding to the Nb3Sn cable in conduit conductors, and in 74 channels devoted to the cooling of the stainless steel case supporting the winding pack. A tool entirely developed inside ANSYS with the APDL language has been created with the aim of computing the temperature distribution in the TF winding pack in different poloidal locations. The tool also allows the assessment of the He temperature during plasma operation in the case cooling channels. The considered heat load is the volumetric nuclear heating computed with the MCNP code in 32 poloidal segments of a TF coil. For each segment, a two-dimensional (2-D) finite-element model is built and a thermal analysis carried out by applying the corresponding heat load, whereas a 1-D thermal-hydraulic code solves the helium transport inside the structure. Steady-state analyses have been done considering the baseline pancake wound configuration. In a second step, a preliminary transient analysis has been carried out, considering the actual ramp up and ramp down of the nuclear heating.
Original languageEnglish
Pages (from-to)1-4
Number of pages4
JournalIEEE Transactions on Applied Superconductivity
Volume28
Publication statusPublished - 2018

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Helium
field coils
helium
Thermal load
ramps
Cooling
cooling
hydraulics
Hydraulics
Heating
heat
heating
Stainless Steel
plasma temperature
Transient analysis
Thermoanalysis
cables
stainless steels
thermal analysis
Cables

All Science Journal Classification (ASJC) codes

  • Electronic, Optical and Magnetic Materials
  • Electrical and Electronic Engineering
  • Condensed Matter Physics

Cite this

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title = "Development of a Two-Dimensional Simplified Tool for the Analysis of the Cooling of the ITER TF Winding Pack",
abstract = "The cooling of the ITER toroidal field (TF) coils winding pack is guaranteed by the circulation of supercritical helium (He) in seven hydraulic circuits corresponding to the Nb3Sn cable in conduit conductors, and in 74 channels devoted to the cooling of the stainless steel case supporting the winding pack. A tool entirely developed inside ANSYS with the APDL language has been created with the aim of computing the temperature distribution in the TF winding pack in different poloidal locations. The tool also allows the assessment of the He temperature during plasma operation in the case cooling channels. The considered heat load is the volumetric nuclear heating computed with the MCNP code in 32 poloidal segments of a TF coil. For each segment, a two-dimensional (2-D) finite-element model is built and a thermal analysis carried out by applying the corresponding heat load, whereas a 1-D thermal-hydraulic code solves the helium transport inside the structure. Steady-state analyses have been done considering the baseline pancake wound configuration. In a second step, a preliminary transient analysis has been carried out, considering the actual ramp up and ramp down of the nuclear heating.",
author = "{Di Maio}, {Pietro Alessandro} and Ruggero Forte and Alfredo Portone and Francesca Cau",
year = "2018",
language = "English",
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journal = "IEEE Transactions on Applied Superconductivity",
issn = "1051-8223",
publisher = "Institute of Electrical and Electronics Engineers Inc.",

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AU - Di Maio, Pietro Alessandro

AU - Forte, Ruggero

AU - Portone, Alfredo

AU - Cau, Francesca

PY - 2018

Y1 - 2018

N2 - The cooling of the ITER toroidal field (TF) coils winding pack is guaranteed by the circulation of supercritical helium (He) in seven hydraulic circuits corresponding to the Nb3Sn cable in conduit conductors, and in 74 channels devoted to the cooling of the stainless steel case supporting the winding pack. A tool entirely developed inside ANSYS with the APDL language has been created with the aim of computing the temperature distribution in the TF winding pack in different poloidal locations. The tool also allows the assessment of the He temperature during plasma operation in the case cooling channels. The considered heat load is the volumetric nuclear heating computed with the MCNP code in 32 poloidal segments of a TF coil. For each segment, a two-dimensional (2-D) finite-element model is built and a thermal analysis carried out by applying the corresponding heat load, whereas a 1-D thermal-hydraulic code solves the helium transport inside the structure. Steady-state analyses have been done considering the baseline pancake wound configuration. In a second step, a preliminary transient analysis has been carried out, considering the actual ramp up and ramp down of the nuclear heating.

AB - The cooling of the ITER toroidal field (TF) coils winding pack is guaranteed by the circulation of supercritical helium (He) in seven hydraulic circuits corresponding to the Nb3Sn cable in conduit conductors, and in 74 channels devoted to the cooling of the stainless steel case supporting the winding pack. A tool entirely developed inside ANSYS with the APDL language has been created with the aim of computing the temperature distribution in the TF winding pack in different poloidal locations. The tool also allows the assessment of the He temperature during plasma operation in the case cooling channels. The considered heat load is the volumetric nuclear heating computed with the MCNP code in 32 poloidal segments of a TF coil. For each segment, a two-dimensional (2-D) finite-element model is built and a thermal analysis carried out by applying the corresponding heat load, whereas a 1-D thermal-hydraulic code solves the helium transport inside the structure. Steady-state analyses have been done considering the baseline pancake wound configuration. In a second step, a preliminary transient analysis has been carried out, considering the actual ramp up and ramp down of the nuclear heating.

UR - http://hdl.handle.net/10447/274827

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JO - IEEE Transactions on Applied Superconductivity

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