Design and Specifications of the ITER TF Coils

Sborchia, C.; Fu, Youkun; Gallix, R.; Jong, C.; Knaster, J.; Mitchell, N.

doi:10.1109/tasc.2008.921339

Cited by 45 publications

(20 citation statements)

References 8 publications

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“…The maximum allowable magnetic field, which occurs on the inboard midplane of the TF coil, is taken as max 13 B T = , a realistic value for current state of the art Niobium-Tin superconducting TF magnets [4,20]. Below this field the magnet should not quench.…”

Section: Engineering and Nuclear Physics Constraints: Quantity Symbolmentioning

confidence: 99%

Designing a tokamak fusion reactor—How does plasma physics fit in?

2015

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Abstract:This paper attempts to bridge the gap between tokamak reactor design and plasma physics. The analysis demonstrates that the overall design of a tokamak fusion reactor is determined almost entirely by the constraints imposed by nuclear physics and fusion engineering. Virtually no plasma physics is required to determine the main design parameters of a reactor:. The one exception is the value of the toroidal current I , which depends upon a combination of engineering and plasma physics. This exception, however, ultimately has a major impact on the feasibility of an attractive tokamak reactor.The analysis shows that the engineering/nuclear physics design makes demands on the plasma physics that must be satisfied in order to generate power. These demands are substituted into the well-known operational constraints arising in tokamak physics: the Troyon limit, Greenwald limit, kink stability limit, and bootstrap fraction limit.Unfortunately, a tokamak reactor designed on the basis of standard engineering and nuclear physics constraints does not scale to a reactor. Too much current is required to achieve the necessary confinement time for ignition. The combination of achievable bootstrap current plus current drive is not sufficient to generate the current demanded by the engineering design. Several possible solutions are discussed in detail involving advances in plasma physics or engineering.The main contribution of the present work is to demonstrate that the basic reactor design and its plasma physics consequences can be determined simply and analytically. 2The analysis thus provides a crisp, compact, logical framework that will hopefully lead to improved physical intuition for connecting plasma physic to tokamak reactor design.3

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Section: Engineering and Nuclear Physics Constraints: Quantity Symbolmentioning

confidence: 99%

Designing a tokamak fusion reactor—How does plasma physics fit in?

2015

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“…A heavy cold structure (STR) is also foreseen to support the forces and moments arising due to the large electromagnetic forces as well as the substantial dead weight. The ITER TF magnets will operate at very high current, approximately at 68 kA [1]. The need of a large cryogenic system is self-explanatory then due to the operation of large SC magnets and CPs as all the cold masses are required to be maintained at 4 K temperature level to get the efficient performance.…”

Section: Introductionmentioning

confidence: 99%

Status of ITER Cryodistribution and Cryoline project

Sarkar

Vaghela

Shah

et al. 2017

IOP Conf. Ser.: Mater. Sci. Eng.

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Abstract. The system of ITER Cryodistribution (CD) and Cryolines (CLs) is an integral interface between the Cryoplant systems and the superconducting (SC) magnets as well as Cryopumps (CPs). The project has progressed from the conceptual stage to the industrial stage. The subsystems are at various stages of design as defined by the project, namely, preliminary design, final design and formal reviews. Significant progresses have been made in the prototypes studies and design validations, such as the CL and cold circulators. While one of the prototype CL is already tested, the other one is in manufacturing phase. Performance test of two cold circulators have been completed. Design requirements are unique due the complexity arising from load specifications, layout constraints, regulatory compliance, operating conditions as well as several hundred interfaces. The present status of the project in terms of technical achievements, implications of the changes and the technical management as well as the risk assessment and its mitigation including path forward towards realization is described.

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“…The construction of the ITER fusion device includes a system of 48 superconducting magnets [2]. These magnets are divided among 4 types: 18 Toroidal Field Coils (TF), 6 Poloidal Field coils (PF), 6 Central Solenoid Modules (CS), and 3 sets of 6 Correction Coils (CC) [2]- [4].…”

Section: Introductionmentioning

confidence: 99%

Risk Mitigation for Cyanate Ester Insulation of Large Magnets Through Cure Optimization

Hill

Munshi

Tupper

et al. 2015

IEEE Trans. Appl. Supercond.

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The toroidal field (TF) coils for the internationally supported ITER nuclear fusion reactor currently being assembled in France will be part of the largest superconducting magnet system ever to be assembled. Due to the relatively high radiation dose expected, the TF coils will utilize a cyanate ester/epoxy blended insulation. It is estimated that this application will represent the single largest use of cyanate ester resins to date. Although magnet coils for the National Spherical Torus Experiment (NSTX) and Wendelstein 7-X have been successfully manufactured using a cyanate ester/epoxy blended insulation, the sheer size of the ITER TF coils create new challenges and concerns with the processing of such large quantities of liquid cyanate ester materials. Handling cyanate ester/epoxy resins can require different equipment and procedures than are required for handling pure epoxies. In particular, cyanate ester/epoxy systems are known for their energetic polymerization, requiring extra care to minimize the risk of an uncontrolled reaction when handled on a large scale. In support of the ITER TF coil manufacturers, LORD Corporation and Composite Technology Development, Inc. (CTD) have qualified two cyanate ester/epoxy resin systems, CTD-425 and CTD-435, and have demonstrated processing robustness and specifically designed cure profiles that will enable coil manufacturers to employ their preferred resin impregnation processes with confidence, even at the very large scale of the ITER project. A description of the cure experiments performed as well as the recommended cure profiles and handling practices for LORD CTD-435 will be presented.Index Terms-Cyanate ester resin, insulation, ITER, TF coil.

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Design and Specifications of the ITER TF Coils

Cited by 45 publications

References 8 publications

Designing a tokamak fusion reactor—How does plasma physics fit in?

Designing a tokamak fusion reactor—How does plasma physics fit in?

Status of ITER Cryodistribution and Cryoline project

Risk Mitigation for Cyanate Ester Insulation of Large Magnets Through Cure Optimization

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