DEMO: Heating and current drive system integration with blanket system

Grossetti, G.; Harman, Jon; Mittwollen, Martin; Poli, E.; Scherer, T.; Späh, P.; Straus, D.; Vaccaro, A.

doi:10.1109/sofe.2013.6635329

Cited by 1 publication

(2 citation statements)

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“…Due to the high complexity of the system, extensive engineering efforts as well as physics studies are required for developing a consistent design that can guarantee high level of reliability and availability [4], mitigating the risks associated to moving targets and many interfaces. Following what reported in [5], in this paper we present a preliminary design and integration study for port plugs dedicated to systems that require an external radial access to the plasma, i.e. Electron Cyclotron (EC) launchers developed by the PPPT Work Package Heating and Current Drive (WPHCD) [6] and devoted to provide localized heating and current drive [7], other heating and current drive systems or diagnostics, all interfacing with in-vessel systems like the breeder blanket.…”

Section: Introductionsupporting

confidence: 52%

“…Following what reported in [5], in this paper we present a preliminary design and integration study for port plugs dedicated to systems that require an external radial access to the plasma, i.e. electron cyclotron (EC) launchers developed by the PPPT work package heating and current drive (WPHCD) [6] and devoted to provide localized heating and current drive [7], other heating and current drive systems or diagnostics, all interfacing with in-vessel systems like the breeder blanket.…”

Section: Introductionsupporting

confidence: 52%

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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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Section: Introductionsupporting

confidence: 52%

Section: Introductionsupporting

confidence: 52%