Electromagnetic analysis of ITER diagnostic port plugs and diagnostic components during plasma events

Y. Zhai, A. Brooks, R. Roccella, J. Guirao, M. Smith, D. Loesser, S. Pak, V. Udintsev, R. Feder, D. Johnson

Research output: Chapter in Book/Report/Conference proceedingConference contribution

2 Scopus citations

Abstract

Eddy current induced electromagnetic (EM) loads during plasma events are the design driver for ITER port plug (PP) structure, diagnostic first wall (DFW), shield module (DSM) and diagnostic system supported by the PP structure. Generic models using commercial software OPERA, MAXWELL and ANSYS are developed and benchmarks are performed for global EM analysis to obtain port-specific design driving EM loads. The 20 degree vessel sector models of the upper and equatorial PP structure take the same ITER TF, CS and PF coil and plasma current (15 MA baseline plasma scenario) as input, then solve for eddy current induced on all passive structural components for various DINA disruption cases. The worst load case can be exponential decay or linear decay of plasma current depending on the dimension and location of diagnostic components inside the PPs. Static and transient magnetic fields from generic models are mapped onto an excel datasheet to establish component design load specification. Three levels of modeling effort are suggested. The global model analysis is used to validate the impact of component design to the PP global system response as well as to study its component dynamic effect as a result of the disruption loads on the PP structure. The local sub-model analysis can be used to extract more accurate EM loads on diagnostics and the excel datasheet of static and transient field maps are used as the initial design load specification for in-port components.

Original languageEnglish (US)
Title of host publication2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015
PublisherInstitute of Electrical and Electronics Engineers Inc.
ISBN (Electronic)9781479982646
DOIs
StatePublished - May 31 2016
Event26th IEEE Symposium on Fusion Engineering, SOFE 2015 - Austin, United States
Duration: May 31 2015Jun 4 2015

Publication series

NameProceedings - Symposium on Fusion Engineering
Volume2016-May

Other

Other26th IEEE Symposium on Fusion Engineering, SOFE 2015
Country/TerritoryUnited States
CityAustin
Period5/31/156/4/15

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Keywords

  • Electromagnetics
  • ITER diagnostics
  • Port plugs

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