Seismic design of the ITER main Tokamak components

Mazzone, G.; Sannazzaro, G.; Schioler, Tyge; Sorı́n, V.

doi:10.1016/j.fusengdes.2010.12.044

Cited by 9 publications

(3 citation statements)

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“…As for fusion machine, the response spectrum analysis (RSA) is the main reference method used for the assessment [9], which consists in a linear dynamic analysis made over the frequency domain of the component to determine the effective acceleration seen by the system under examination. In order to verify the design of LWR feedthrough under seismic loads, an additional equivalent static analysis is made on top of RSA.…”

Section: Seismic Analysis Approachmentioning

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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Section: Seismic Analysis Approachmentioning

confidence: 99%

Structural integrity assessment for ITER lower VS coil feedthrough

Peng¹,

Mariani²,

Vostner³

et al. 2021

Nucl. Fusion

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“…All the ITER hardware has to be tested to withstand such seismic events. There are two methods of seismic load analysis accepted by the ITER community [6]: the equivalent static analysis and the response spectra method. Both these analyses are planned for use in assessment of the diagnostic in-vessel hardware design quality.…”

Section: Seismic Analysismentioning

confidence: 99%

“…Below we show the equivalent static analysis results. According to [6] we have taken into account the main natural frequencies of the diagnostic rack prototype. The most important diagnostic rack natural frequencies selected from one hundred of the lowest natural frequencies and its mass participation in each direction were obtained from the modal analysis of 3D FE model of the diagnostic rack prototype (see table 2).…”

Section: Seismic Analysismentioning

confidence: 99%

The ITER divertor Thomson scattering system: engineering and advanced hardware solutions

et al. 2012

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A divertor Thomson scattering (TS) system being developed for ITER has incorporated proven solutions from currently available TS systems. On the other hand any ITER diagnostic has to operate in a hostile environment and very restricted access geometry. Therefore the operation in an environment of intensive stray light, plasma background radiation, the necessity meet the requirement using only a 20 mm gap between divertor cassettes for plasma diagnosis as well as to measure plasma temperatures as low as 1 eV severely constrain the divertor TS diagnostic design. The challenging solutions of this novel diagnostic system which has to ensure its steady performance and also the operability and maintenance are the focus of this report. One of the most demanding parts of the in-vessel diagnostic equipment development is the design assessment using different engineering analyses. The task definition and first results of thermal, e/m and seismic analyses are provided. The process of further improving of the design involves identification of

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