Options for shielding Tokamak Cooling Water electrical components against high magnetic fields

Fusion Engineering(2011)

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Abstract
The Tokamak Cooling Water System (TCWS) Instrumentation and Control (I&C) components of ITER will be located in areas of relatively high magnetic fields. Previous tests on electrical and I&C components have indicated that shielding will be required to protect these components from such magnetic fields. To accomplish this, studies were performed by AREVA Federal Services (AFS) in support of the TCWS Design project with the intent of identifying an optimal solution for shielding I&C components. This paper presents a summary of these studies and presents design options for providing magnetic shielding to ITER TCWS I&C components and electrical equipment that are susceptible to the magnetic fields present.
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tokamak devices,fusion reactor instrumentation,magnetic shielding,plasma toroidal confinement,iter tcws control components,iter tcws instrumentation,tcws design project,electrical component shielding,high magnetic fields,tokamak cooling water system electrical components,tokamak instrumentation,electromagnetic compatibility,stray magnetic fields,switches,tokamaks,magnetic field
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