Development of the ITER PF Coils

Lim, Byung Su; Simon, Fabrice; Ilin, Y.; Gung, C.; Boyer, C.; Beemsterboer, C.; Valente, P.; Lelekhov, S.A.; Mitchell, N.

doi:10.1109/tasc.2011.2174564

Cited by 16 publications

(7 citation statements)

References 3 publications

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“…As illustrated in Figure 3, the tokamak cryostat is 28 m tall and 29 m in diameter, which corresponds more or less to the size of the Jefferson memorial in Washington DC. The ITER magnet system is fully superconducting and includes 4 different types of coils (see Figure 4) [4]  18 Toroidal Field (TF) coils, located around the plasma chamber, to be manufactured in EU [5] and Japan [6],  a Central Solenoid (CS), made up of a stack of 6 modules and positioned at the machine centre, to be manufactured in the US [7],  6 Poloidal Field (PF) coils, surrounding the TF coils, whose manufacture is the responsibility of RF (for PF1) and EU (for PF2 to 6) [8],  9 pairs of Correction Coils (CCs), attached to the PF coils, to be manufactured in China [9].…”

Section: Iter Tokamak and Magnet Systemmentioning

confidence: 99%

Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

170

118

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Taking the relay of the Large Hadron Collider (LHC) at CERN, ITER has become the largest project in applied superconductivity. In addition to its technical complexity, ITER is also a management challenge as it relies on an unprecedented collaboration of 7 partners, representing more than half of the world population, who provide 90% of the components as in-kind contributions. The ITER magnet system has a stored energy of 51 GJ and involves 6 of the ITER partners. The coils are wound from Cable-In-Conduit Conductors (CICCs) made up of superconducting and copper strands assembled into a fully transposed, rope-type cable, inserted into a conduit of butt-welded austenitic steel tubes. The conductors for the Toroidal Field (TF) and Central Solenoid (CS) coils require about 500 tons of Nb 3 Sn strands while the Poloidal Field (PF) and Correction Coil (CC) and busbar conductors need around 250 tons of Nb-Ti strands. The required amount of Nb 3 Sn strands far exceeds pre-existing industrial capacity and has called for a significant worldwide production scale up. The TF conductors are the first ITER components to be mass produced and are more than 50% complete. During its life time, the CS coil will have to sustain several tens of thousands of electromagnetic (EM) cycles to high current and field conditions, way beyond anything a large Nb 3 Sn coil has ever experienced. Following a comprehensive R&D program, a technical solution has been found for the CS conductor, which ensures stable performance versus EM and thermal cycling. Productions of PF, CC and busbar conductors are also underway. After an introduction to the ITER project and magnet system, we describe the ITER conductor procurements and the Quality Assurance/Quality Control programs that have been implemented to ensure production uniformity across numerous suppliers. Then, we provide examples of technical challenges that have been encountered and we present a status of ITER conductor production worldwide.

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Section: Iter Tokamak and Magnet Systemmentioning

confidence: 99%

Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

170

118

View full text Add to dashboard Cite

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“…-a vertical stabilization controller (VSC) controlling plasma vertical position or speed using the VS3 circuit voltage (see [6][7][8] for a description of ITER poloidal field system (PF system); -a current control (CC) controlling currents in the active coils (central solenoid (CS) coils and P1-P6 coils) using voltage on active coil power supplies; -a shape controller (SC) controlling gaps between the separatrix and wall or other shape parameters using currents (reference currents to the CC) on the active coils.…”

Section: Main Assumptions and Models Used In Predictive Transport Mod...mentioning

confidence: 99%

“…Self-consistent predictive simulation of ITER scenarios is a very important and widely used tool for the exploration of the operational space and for scenario optimization [5][6][7][8][9][10][11][12][13][14][15][16][17]. It can also provide an assessment of the compatibility of the developed scenarios (including fast transient events) with machine constraints; in particular with the poloidal field (PF) coil system, with heating and current drive (H&CD), fuelling, particle and energy exhaust systems.…”

Section: Introductionmentioning

confidence: 99%

Self-consistent simulation of plasma scenarios for ITER using a combination of 1.5D transport codes and free-boundary equilibrium codes

et al. 2013

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Self-consistent transport simulation of ITER scenarios is a very important tool for the exploration of the operational space and for scenario optimization. It also provides an assessment of the compatibility of developed scenarios (which include fast transient events) with machine constraints, in particular with the poloidal field coil system, heating and current drive, fuelling and particle and energy exhaust systems. This paper discusses results of predictive modelling of all reference ITER scenarios and variants using two suites of linked transport and equilibrium codes. The first suite consisting of the 1.5D core/2D SOL code JINTRAC (Wiesen S. et al 2008 JINTRAC-JET modelling suite JET ITC-Report) and the free-boundary equilibrium evolution code CREATE-NL (Albanese R. et al 2003 ISEM 2003 (Versailles, France); Albanese R. et al 2004 Nucl. Fusion 44 999), was mainly used to simulate the inductive D–T reference Scenario-2 with fusion gain Q = 10 and its variants in H, D and He (including ITER scenarios with reduced current and toroidal field). The second suite of codes was used mainly for the modelling of hybrid and steady-state ITER scenarios. It combines the 1.5D core transport code CRONOS (Artaud J.F. et al 2010 Nucl. Fusion 50 043001) and the free-boundary equilibrium evolution code DINA-CH (Kim S.H. et al 2009 Plasma Phys. Control. Fusion 51 105007).

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“…The six PF coils (PF1 to PF6) [8], [9], are attached to the TF coil cases through flexible plates or sliding supports allowing radial displacements. The square conductor provides the coil structural support.…”

Section: System Overview and Integrationmentioning

confidence: 99%

The ITER Magnets: Design and Construction Status

Mitchell

Devred

Libeyre

et al. 2012

IEEE Trans. Appl. Supercond.

Self Cite

184

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The ITER magnet procurement is now well underway. The magnet systems consist of 4 superconducting coil sets (toroidal field (TF), poloidal field (PF), central solenoid (CS) and correction coils (CC)) which use both NbTi and -based conductors. The magnets sit at the core of the ITER machine and are tightly integrated with each other and the main vacuum vessel. The total weight of the system is about 10000 t, of which about 500 t are strands and 250 t, NbTi. The reaction of the magnetic forces is a delicate balance that requires tight control of tolerances and the use of high-strength, fatigue-resistance steel forgings. Integration and support of the coils and their supplies, while maintaining the necessary tolerances and clearance gaps, have been completed in steps, the last being the inclusion of the feeder systems. Twenty-one procurement agreements have now been signed with 6 of the ITER Domestic Agencies for all of the magnets together with the supporting feeder subsystems. All of them except one (for the CS coils) are so-called Build to Print agreements where the IO provides the detailed design including full three-dimensional CAD models. The production of the first components is underway (about 175 t of strand was finished by July 2011) and manufacturing prototypes of TF coil components are being completed. The paper will present a design overview and the manufacturing status.

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Development of the ITER PF Coils

Cited by 16 publications

References 3 publications

Challenges and status of ITER conductor production

Challenges and status of ITER conductor production

Self-consistent simulation of plasma scenarios for ITER using a combination of 1.5D transport codes and free-boundary equilibrium codes

The ITER Magnets: Design and Construction Status

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