Cryogenic Engineering Design of the ITER Superconducting Magnet Feeders

Sahu, A. K.; Gung, C.; Lü, Kun; Bauer, P.; Devred, A.; Song, Yuntao; Bi, Yong; Il’in, I. V.; Rodriguez-Mateos, F.; Dolgetta, N.; Mitchell, N.

doi:10.1109/tasc.2011.2181936

Cited by 9 publications

(6 citation statements)

References 7 publications

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“…The ITER TF coils, for instance, are split into nine sectors each containing two coils, resulting in 11 s for the time constant [123]. As sketched in figure 22, nine discharge units and nine pairs of HTS current leads and long bus bars are then necessary, leading to demanding cryogenic requirements [124]. Each discharge unit is essentially composed of a discharge resistor, mechanical switch, vacuum and pyro circuit breakers, which are essential to ensure backup switching in case of any failures in the current commutation unit.…”

Section: Statusmentioning

confidence: 99%

Superconductors for fusion: a roadmap

Mitchell

Zheng

Vorpahl³

et al. 2021

Supercond. Sci. Technol.

111

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With the first tokamak designed for full nuclear operation now well into final assembly (ITER), and a major new research tokamak starting commissioning (JT60SA), nuclear fusion is becoming a mainstream potential energy source for the future. A critical part of the viability of magnetic confinement for fusion is superconductor technology. The experience gained and lessons learned in the application of this technology to ITER and JT60SA, together with new and improved superconducting materials, is opening multiple routes to commercial fusion reactors. The objective of this roadmap is, through a series of short articles, to outline some of these routes and the materials/technologies that go with them.

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Section: Statusmentioning

confidence: 99%

Superconductors for fusion: a roadmap

Mitchell

Zheng

Vorpahl³

et al. 2021

Supercond. Sci. Technol.

111

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“…The current and coolant of the superconducting magnet are supplied by the Feeder, and for the purpose of assembly and mechanical redundancy, the feeder is divided into Coil-Terminal-Box (CTB), S-Bend-Box (SBB), Cryostat Feed-through (CFT), and In-Cryostat Feeder (ICF) [9,[21][22][23]. The following are the design requirements from ITER organization:…”

Section: The Design Of the Petal Overlap Superconducting Jointmentioning

confidence: 99%

Some Research Method about Superconducting Magnet Systems of TOKAMAK

Rong¹

2022

Advances in Fusion Energy Research - From Theory to Models, Algorithms, and Applications

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The superconducting magnet operates in conditions of complex electromagnetics, which could cause hysteresis loss and coupling losses, the so-called AC losses. In this chapter, the AC losses calculation of superconductor will be discussed in detail. Usually, the superconducting magnets are wound by superconducting coils, which are twisted by superconducting wires. The length of superconducting wires is hundreds of meters, while the length of coils is millions of meters; thus, joints are needed to join the coils. The design of different patterns of joints, such as twin-box joint, butt joint, and petal overlap joint, will be introduced in detail. Joule heat and AC losses in the joint may cause locality quench, and if the design stability margin of the magnet could not cover the joule heat and losses, the locality quench will cause global quench of the magnet. The temperature rise caused by joule heat and AC losses will be discussed in detail. Furthermore, the magnetic Lorentz force and mechanical displacement could cause locality quench, which may cause a global quench, once the coolant could not take away the heating pulse. The simulation of the stability and quench behavior of the superconducting cable-in-conduit conductor will be introduced in detail.

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“…2. STR feeders have no bus bar, no CL, and no instrumentation pipe running between feeder 1051-8223/$31.00 © 2012 and coil compared to coil feeders of ITER magnets [3], [4]. They have only pipes, valves and some sensors.…”

Section: Pfd (Process Flow Diagram)mentioning

confidence: 99%

“…During fast discharge, there will be high transient heat loads, but analysis shows that the maximum pressure is 20 bar with pressure release only on supply side. Each of these pressure release systems has the same configuration and set pressures as used for the coil feeders [3].…”

Section: B Pressure Release System For Accidental Casesmentioning

confidence: 99%

Design Approach and Analysis Results for Structure Feeders of ITER Magnets

Sahu

Dolgetta

Gung

et al. 2012

IEEE Trans. Appl. Supercond.

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The superconducting magnet system of ITER has 5,000 tons of cold mass as steel structures to support the gravity and electromagnetic forces. These steel structures need to be maintained at 4.4 K during magnet operations. The magnet system has three STR (structure) feeders for distribution, monitoring and control of helium to remove heat loads from these large steel structures during cool down and normal operation. One SHe (supercritical helium) circulation pump for flow rate of 2.7 kg/s, in a closed loop is used only for cooling of structures, and these 3 STR feeders are part of this loop. Each STR feeder has 3 main components: SCVB (structure cooling valve box), CFT (cryostat feed through) and ICF (in-cryostat feeder). Unlike the coil feeders, STR feeders do not have bus bars, current leads & SBB ("S"-bend box), and present some difference in the design approach. The SCVB is placed outside the enclosure of the nuclear radiation shield and hence contains elements needing maintenance like valves and instruments required for diagnosis and operation of the cooling paths. Each SCVB has to accommodate about 20 valves within a limited available space. Some SHe lines will have running length of about 50 m from SCVB to coil structures, but the layout is such that the use of expansion joints can be avoided. The details of the design approach and analysis results will be presented in this paper.

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Cryogenic Engineering Design of the ITER Superconducting Magnet Feeders

Cited by 9 publications

References 7 publications

Superconductors for fusion: a roadmap

Superconductors for fusion: a roadmap

Some Research Method about Superconducting Magnet Systems of TOKAMAK

Design Approach and Analysis Results for Structure Feeders of ITER Magnets

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