Erratum: Examinations for leak tightness of actively cooled components in ITER and fusion devices (2017 Phys. Scr. 2017 014045)

PHYSICA SCRIPTA(2017)

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摘要
Any leak in one of the ITER actively cooled components would cause significant consequences for machine operations; therefore, the risk of leak must be minimized as much as possible. In this paper, the strategy of examination to ensure leak tightness of the ITER internal components (i.e. examination of base materials, vacuum boundary joints and final components) and the hydraulic parameters for ITER internal components are summarized. The experiences of component tests, especially hot helium leak tests in recent fusion devices, were reviewed and the parameters were discussed. Through these experiences, it was confirmed that the hot He leak test was effective to detect small leak paths which were not always possible to detect by volumetric examination due to limited spatial resolution.
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关键词
leak test,high heat flux,ITER,actively cooled component,plasma-facing component,divertor,blanket
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