Nuclear engineering of diagnostic port plugs on ITER

Pitcher, C.S.; Barnsley, R.; Feder, R.; Hu, Qiya; Loesser, G. D.; Lyublin, B. V.; Padasalagi, Shrishail; Pak, S.; Reichle, R.; Sato, Kazuyoshi; Udintsev, V. S.; Walker, Chris; Walsh, Michael J.; Zhai, Yuhu

doi:10.1016/j.fusengdes.2012.01.043

Cited by 17 publications

(4 citation statements)

References 12 publications

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“…ECE, CTS and some reflectometry systems will also be installed in diagnostic port-plugs [7] where more space is available. Depending on the system, quasi-optics or over-sized corrugated waveguides will be used.…”

Section: In-vessel Waveguidesmentioning

confidence: 99%

Design and development activities for in-vessel and in-port components of ITER microwave diagnostics

Sirinelli,

Antonov,

Feder

et al. 2015

Preprint

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The ITER tokamak will be operating with 5 microwave diagnostic systems. While they rely on different physics, they share a common need: transmitting low and high power microwave in the range of 12 GHz to 1000 GHz (different bandwidths for different diagnostics) between the plasma and a diagnostic area tens of meters away. The designs proposed for vacuum windows, in-vessel waveguides and antennas are presented together with the development activities needed to finalise this work.

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Section: In-vessel Waveguidesmentioning

confidence: 99%

Design and development activities for in-vessel and in-port components of ITER microwave diagnostics

Sirinelli,

Antonov,

Feder

et al. 2015

Preprint

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“…To make the scattering angle be close to a right angle, the first collection mirror is located around the front end of the drawer (details of the drawer are described in ref. [8]). Optical features of the collection optics in this paper were kept the same as the previous design [9].…”

Section: Diagnostic Geometrymentioning

confidence: 99%

Progresses in development of the ITER edge Thomson scattering system

et al. 2013

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This paper includes discussions of spatial resolution and accuracy of the edge Thomson scattering system in ITER (ITER ETS). In the present design, the dominant factor for spatial resolution degradation relative to the scattering length is aberrations of the collection optics. A scattering length of approximately 4 mm is acceptable to obtain a spatial resolution of 5 mm. Statistical errors were evaluated according to measurement accuracy. Since the background light during ITER plasma discharge is much stronger than the Thomson scattering, the laser pulse duration is one of the most crucial specifications to obtain accurate measurements. The impact of fast sampling relative to current integration was also investigated. It is expected that the measurement accuracy improves when the waveform of the scattered light is sampled directly particularly for low density measurement.

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“…The port plug assembly provides necessary structural support of diagnostic systems while allowing diagnostic access to the plasma. [1][2] The DFW design is challenging due to the conflicting set of requirements for diagnostics protection from high plasma heating and nuclear radiation while allowing diagnostic viewing access. [3] Figure 1 shows the upper and equatorial port plugs inside ITER Tokamak.…”

Section: Introductionmentioning

confidence: 99%

“…Each of the three DFW-DSM assembled cassettes inside an equatorial port plug (one cassette for each upper port) is supported by the PP structure via load bearing pads and a set of sliding rails attached to the PP structure. [1,3] Thermal fatigue total strain range between heating and dwelling phase of the 6 mm thick first wall dictates the maximum number of thermal cycles allowed. Stresses on DFW attachment tabs under disruption loads drive the design and optimization of the tab geometry and the bolt joint selection at the DFW-DSM interface.…”

Section: Introductionmentioning

confidence: 99%

Multiphysics Engineering Analysis for ITER Diagnostic First Wall and Shield Module Design*

Zhai¹,

Loesser²,

Smith³

et al. 2015

eee

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ITER diagnostic first walls (DFWs) and diagnostic shield modules (DSMs) inside the port plugs (PPs) are designed to protect diagnostic instrument and components from a harsh plasma environment and provide structural support while allowing for diagnostic access to the plasma. The design of DFWs and DSMs are driven by 1) plasma radiation and nuclear heating during normal operation 2) electromagnetic loads during plasma events and associate component structural responses. A multi-physics engineering analysis protocol for the design has been established at Princeton Plasma Physics Laboratory and it was used for the design of ITER DFWs and DSMs. The analyses were performed to address challenging design issues based on resultant stresses and deflections of the DFW-DSM-PP assembly for the main load cases. ITER Structural Design Criteria for In-Vessel Components (SDC-IC) required for design by analysis and three major issues driving the mechanical design of ITER DFWs are discussed. The general guidelines for the DSM design have been established as a result of design parametric studies.

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Nuclear engineering of diagnostic port plugs on ITER

Cited by 17 publications

References 12 publications

Design and development activities for in-vessel and in-port components of ITER microwave diagnostics

Design and development activities for in-vessel and in-port components of ITER microwave diagnostics

Progresses in development of the ITER edge Thomson scattering system

Multiphysics Engineering Analysis for ITER Diagnostic First Wall and Shield Module Design*

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