The ITER In-Vessel Coils – design finalization and challenges

Vostner, A.; Bontemps, Vincent; Encheva, A.; Jin, Huan; Laquiere, Julien; Macioce, Davide; Mariani, Nicola; McIntosh, S.; Peng, Xuebing; Singh, S.; Spigo, G.; Tronza, V.

doi:10.1016/j.fusengdes.2019.02.113

Cited by 16 publications

(3 citation statements)

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“…At high plasma performance, the control of magnetohydrodynamic (MHD) instabilities (Lao et al, 2020) is particularly critical in ITER to maintain the fusion burn and to avoid potential damage to the first wall. For example, edge localized modes (ELMs), which expel short bursts of heat and particles, are controlled by a set of 27 in-vessel copper coils (Vostner et al, 2019). Disruptions, which produce high transient heat and electromechanical loads on in-vessel structures, must be avoided or their effects mitigated (see Lao et al, 2020;Zohm, 2020).…”

Section: Auxiliary and Plant Systemsmentioning

confidence: 99%

Magnetic Confinement Fusion—Development Facilities

Donné

Federici²,

Ibarra

et al. 2021

Encyclopedia of Nuclear Energy

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Section: Auxiliary and Plant Systemsmentioning

confidence: 99%

Magnetic Confinement Fusion—Development Facilities

Donné

Federici²,

Ibarra

et al. 2021

Encyclopedia of Nuclear Energy

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Section: Introductionmentioning

confidence: 99%

“…The upper and lower vertical stabilization coils (UPR VS and LWR VS) [1][2][3], are designed for the feedback control of the plasma vertical displacement in all scenarios with elongated plasma cross-section. Each coil consists of four turns toroidal loops, located at upper or lower portion of vacuum vessel (VV) [1]. The conductor of VS coils is made of a water-cooled Cu core surrounded by a compacted ceramic layer (MgO) for electrical insulation and by a stainless steel jacket for mechanical support.…”

Section: Introductionmentioning

confidence: 99%

Structural integrity assessment for ITER lower VS coil feedthrough

Peng¹,

Mariani²,

Vostner³

et al. 2021

Nucl. Fusion

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The ITER vertical stabilization coil system is designed to provide fast plasma stabilization in all scenarios with elongated plasma cross-section. It consists of two water-cooled coils located in upper and lower portions of the vacuum vessel (VV), with feedthroughs responsible for the transfer of electricity and cooling water across the vacuum boundary of VV. Depending on location, the feedthroughs can be divided into upper port feedthroughs (UPR feedthroughs) and lower port feedthroughs (LWR feedthroughs), each family sharing the same design. Both designs are subject to demanding operation scheme, a severe working environment and the presence of interfacing components, which impose important thermal, electromagnetic and seismic loads on the components. In particular, the LWR feedthrough, object of present paper, is more impacted by seismic loads due to the more flexible structure compared to the UPR feedthrough. During the worst seismic event, it is subjected to a vertical acceleration of 28.8 m s−2, acting on an effective mass of 249.9 kg at its first order modal mode. Furthermore, the current circulating in the conductor of the LWR feedthrough, impose significant linear forces, up to 27.7 kN m−1 during normal operation and 30.3 kN m−1 during categories I & II abnormal plasma events, respectively. Finally, the effect of differential thermal expansions of interfacing structures imposes a relative displacement between the supports up to 32.9 mm in X (radial) direction and up to 14.67 mm in Z (vertical) direction, during baking. Being part of the vacuum boundary, the feedthrough must assure confinement function under all normal and accidental loading conditions, with proper structural integrity assessment by applying analysis approach and design criteria foreseen by the applicable nuclear codes. The paper details the load types and categories, the analysis methodologies, the structural design criteria, and the assessment results in views of static stress and fatigue for the LWR feedthrough. This study could be a comprehensive reference for the structural integrity assessment of other similar components in fusion devices.

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Challenges and status of the ITER IVC conductor qualification process in China

Liu

Wang³

et al. 2019

Fusion Engineering and Design

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The ITER In-Vessel Coils – design finalization and challenges

Cited by 16 publications

References 1 publication

Magnetic Confinement Fusion—Development Facilities

Magnetic Confinement Fusion—Development Facilities

Structural integrity assessment for ITER lower VS coil feedthrough

Challenges and status of the ITER IVC conductor qualification process in China

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