Final design of the generic equatorial port plug structure for ITER diagnostic systems

Udintsev, V. S.; Maquet, P.; Alexandrov, E.; Casal, N.; Cuenca, D.; Drevon, J.-M.; Feder, R.; Friconneau, Jean-Pierre; Giacomin, T.; Guirao, J.; Iglesias, Silvia; Josseaume, Fabien; Levesy, B.; Loesser, D.; Ordieres, J.; Quinn, E.; Pak, S.; Penot, C.; Pitcher, C.S.; Portales, M.; Proust, M.; Suárez, Alejandro; Seyvet, F.; Tanchuk, V.; Utin, Yuri; Vacas, C.; Vasseur, C.; Walsh, Michael J.

doi:10.1016/j.fusengdes.2015.05.021

Cited by 22 publications

(6 citation statements)

References 2 publications

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“…In ITER, the installation of plasma diagnostics and auxiliary heating front-end systems in the ports [13] of the upper and equatorial levels is foreseen in so-called port plugs (PPs) [14,15]. These PPs are designed as cantilevers.…”

Section: Application Of Iter Solutionsmentioning

confidence: 99%

DEMO vacuum vessel port closure plate sealing and fixation activities

Haertl

Bachmann

Franke

et al. 2023

Fusion Engineering and Design

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Section: Application Of Iter Solutionsmentioning

confidence: 99%

DEMO vacuum vessel port closure plate sealing and fixation activities

Haertl

Bachmann

Franke

et al. 2023

Fusion Engineering and Design

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“…They are called Blanket Separated Design (BSD) and a Blanket Integrated Design (BID), and they are more detail discussed in §4.1 and §4.2, respectively. The former stops behind the BSS of the OB-MMS, while the latter follow a similar design implemented for ITER port plugs for diagnostics and ECH&CD systems (see [16] and [17], respectively), that is it physically penetrates the OB-MMS up to the plasma. For this reason a blanket shield module is integrated into the port plug structure.…”

Section: Port Plug Conceptsmentioning

confidence: 99%

DEMO port plug design and integration studies

et al. 2017

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The EUROfusion Consortium established in 2014 and composed by European Fusion Laboratories, and in particular the Power Plant Physics and Technology department aims to develop a conceptual design for the Fusion DEMOnstration Power Plant, DEMO. With respect to present experimental machines and ITER, the main goals of DEMO are to produce electricity continuously for a period of about 2 hours, with a net electrical power output of a few hundreds of MW, and to allow Tritium self-sufficient breeding with an adequately high margin in order to guarantee its planned operational schedule, including all planned maintenance intervals. This will eliminate the need to import tritium fuel from external sources during operations. In order to achieve these goals, extensive engineering efforts as well as physics studies are required to develop a design that can ensure a high level of plant reliability and availability. In particular, interfaces between systems must be addressed at a very early phase of the project, in order to proceed consistently. In this paper we present a preliminary design and integration study, based on physics assessments for the EU DEMO1 Baseline 2015 with an Aspect Ratio of 3.1 and 18 Toroidal Field Coils, for the DEMO port plugs. These aim to host systems like Electron Cyclotron Heating launchers currently developed within the Work Package Heating and Current Drive that need an external radial access to the plasma and through in-vessel systems like the breeder blanket. A similar approach shown here could be in principle followed by other systems, e.g. other heating and current drive systems or diagnostics. The work addresses the interfaces between the port plug and the blanket considering the Helium-Cooled Pebble Bed and the Water Cooled Lithium Lead which are two of four breeding blanket concepts under investigation in Europe within the Power Plant Physics and Technology Programme: the required openings will be evaluated in terms of their impact onto the blanket segments thermo-mechanical and nuclear design considering mechanical integration aspects but also their impact on Tritium Breeding Ratio. Since DEMO is still in a pre-conceptual phase, the same methodology is applicable to the other two blanket concepts, as well.

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“…The GEPP is designed to survive throughout the ITER lifetime for 20 years, 30,000 plasma discharges and 3000 disruptions. More details on the GEPPs can be found in [2].…”

Section: Diagnostic Generic Equatorial Port Plug (Gepp)mentioning

confidence: 99%