Design and Analysis Progress of ITER Diagnostic Equatorial Port #09

Zhai, Yuhu; Basile, Allan; Feder, R.; Wang, W.; Chen, Jingping; Khodak, Andrei; Klabacha, Jonathan Paul; Johnson, D.; Hause, M.; Messineo, M.; Zhang, Han; Gonzalez-Teodoro, Jorge Rafael; Guirao, Julio; Iglesias, Silvia

doi:10.1109/TPS.2017.2788188

Title: Design and Analysis Progress of ITER Diagnostic Equatorial Port #09

Abstract

ITER is the world's largest fusion device currently under construction in the South of France with >50 diagnostic systems to be installed inside the port plugs (PPs), the interspace (IS), or the port cell region of various diagnostic ports. The plasma facing diagnostic first wall (DFW) and its supporting diagnostic shield modules (DSM) are designed to protect front-end diagnostics from plasma neutron and plasma radiation, while providing apertures for diagnostic access to the plasma. The design of ITER port plug structures including the DFW and the DSM is largely driven by the electromagnetic loads included on the PP structural components during plasma major disruptions and the vertical displacement events (VDEs). Unlike DFW and DSM, the design of diagnostic system, however, is likely driven by the steady-state thermal loads from plasma volumetric and surface heating and the dynamic response of the in-port components attached to the port-specific DSM or closure plate under transient loads induced on the vacuum vessel and the port extension during asymmetric VDEs. Three tenant diagnostic systems are integrated into the equatorial port 09. The toroidal interferometer/polarimeter, or TIP system, is installed in the left drawer (DSM3, left looking from plasma) for measuring the plasma density so tomore »« less

Authors:

^[1]; Basile, Allan ^[1]; Feder, R. ^[1]; Wang, W. ^[1]; Chen, Jingping ^[1];

^[1]; Klabacha, Jonathan Paul ^[1]; Johnson, D. ^[1]; Hause, M. ^[1]; Messineo, M. ^[1];

^[1];

^[1]; Guirao, Julio ^[2]; Iglesias, Silvia ^[2]

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
ITER Organization, St. Paul lez Durance (France)

Publication Date:: Wed Jan 17 00:00:00 EST 2018

Research Org.:: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1460739

Grant/Contract Number:: AC02-09CH11466

Resource Type:: Accepted Manuscript

Journal Name:: IEEE Transactions on Plasma Science

Additional Journal Information:: Journal Volume: 46; Journal Issue: 5; Journal ID: ISSN 0093-3813

Publisher:: IEEE

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER diagnostics; multiphysics analysis; port plug integration

Citation Formats


                    Zhai, Yuhu, Basile, Allan, Feder, R., Wang, W., Chen, Jingping, Khodak, Andrei, Klabacha, Jonathan Paul, Johnson, D., Hause, M., Messineo, M., Zhang, Han, Gonzalez-Teodoro, Jorge Rafael, Guirao, Julio, and Iglesias, Silvia. Design and Analysis Progress of ITER Diagnostic Equatorial Port #09.  United States: N. p., 2018. 
Web.  doi:10.1109/TPS.2017.2788188.

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                    Zhai, Yuhu, Basile, Allan, Feder, R., Wang, W., Chen, Jingping, Khodak, Andrei, Klabacha, Jonathan Paul, Johnson, D., Hause, M., Messineo, M., Zhang, Han, Gonzalez-Teodoro, Jorge Rafael, Guirao, Julio, & Iglesias, Silvia. Design and Analysis Progress of ITER Diagnostic Equatorial Port #09.  United States.  https://doi.org/10.1109/TPS.2017.2788188

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                    Zhai, Yuhu, Basile, Allan, Feder, R., Wang, W., Chen, Jingping, Khodak, Andrei, Klabacha, Jonathan Paul, Johnson, D., Hause, M., Messineo, M., Zhang, Han, Gonzalez-Teodoro, Jorge Rafael, Guirao, Julio, and Iglesias, Silvia. Wed .  
"Design and Analysis Progress of ITER Diagnostic Equatorial Port #09".  United States.  https://doi.org/10.1109/TPS.2017.2788188.  https://www.osti.gov/servlets/purl/1460739.

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@article{osti_1460739,

  title        = {Design and Analysis Progress of ITER Diagnostic Equatorial Port #09},

  author       = {Zhai, Yuhu and Basile, Allan and Feder, R. and Wang, W. and Chen, Jingping and Khodak, Andrei and Klabacha, Jonathan Paul and Johnson, D. and Hause, M. and Messineo, M. and Zhang, Han and Gonzalez-Teodoro, Jorge Rafael and Guirao, Julio and Iglesias, Silvia},

  abstractNote = {ITER is the world's largest fusion device currently under construction in the South of France with >50 diagnostic systems to be installed inside the port plugs (PPs), the interspace (IS), or the port cell region of various diagnostic ports. The plasma facing diagnostic first wall (DFW) and its supporting diagnostic shield modules (DSM) are designed to protect front-end diagnostics from plasma neutron and plasma radiation, while providing apertures for diagnostic access to the plasma. The design of ITER port plug structures including the DFW and the DSM is largely driven by the electromagnetic loads included on the PP structural components during plasma major disruptions and the vertical displacement events (VDEs). Unlike DFW and DSM, the design of diagnostic system, however, is likely driven by the steady-state thermal loads from plasma volumetric and surface heating and the dynamic response of the in-port components attached to the port-specific DSM or closure plate under transient loads induced on the vacuum vessel and the port extension during asymmetric VDEs. Three tenant diagnostic systems are integrated into the equatorial port 09. The toroidal interferometer/polarimeter, or TIP system, is installed in the left drawer (DSM3, left looking from plasma) for measuring the plasma density so to control the fuel input. The electron cyclotron emission (ECE) system is installed in the middle drawer (DSM2) to provide the high spatial and temporal resolution measurements of electron temperature evolution and the electron thermal transport inferences. The visible/infrared wide angle viewing system is installed in the right drawer (DSM1) to provide visible and infrared viewing and temperature data of the first wall for its protection in support of machine operation. The port plug integration design and multiphysics analyses are performed following port integration requirements including the weight limit (45 tones total), shut down dose rate limits, the cooling/heating and structural integrity validation. Mass distribution for TIP and ECE DSMs has been optimized to minimize the total weight by a new design of the boron carbide shielding pocket. Furthermore, the lightened DSM maintains its front-end load distribution and the structural stiffness with minimum impact to the DFW so to better protect on-board diagnostics; while still provides sufficient front-end stiffness for its structural integrity as well as the diagnostics function requirements.},

  doi          = {10.1109/TPS.2017.2788188},

  journal      = {IEEE Transactions on Plasma Science},

  number       = 5,

  volume       = 46,

  place        = {United States},

  year         = {Wed Jan 17 00:00:00 EST 2018},

  month        = {Wed Jan 17 00:00:00 EST 2018}

}

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Figure 1: ITER diagnostic ports and US ITER diagnostics scope

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