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27th IEEE Symposium on Fusion Engineering

4–8 Jun 2017
Marriott Shanghai City Center
Asia/Shanghai timezone

Session

M.OA2: Divertors and High Heat Flux Components

M.OA2
5 Jun 2017, 10:40
Marriott Shanghai City Center

Marriott Shanghai City Center

555 Xi Zang Road (Middle), Huangpu District Shanghai 200003 China

Presentation materials

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  1. 83. Design and test of W7-X water-cooled Divertor Scraper
    Dr Jean Boscary (Max Planck Institute for Plasma Physics)
    05/06/2017, 10:40
    Divertors and high heat flux components
    Invited Oral

    For steady state operation up to 30 minutes pulse duration of the stellarator Wendelstein 7-X, an actively water-cooled divertor will replace the currently installed adiabatically loaded divertor designed for maximal 10 second plasma pulses. Heat load calculations taking into account the effect of bootstrap current have indicated the possible overloading of the ends of the divertor beyond...

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  2. 513. Modeling and Experimental Validation of Physics Enabled by W7-X Scraper Element Divertor Components
    Dr Jeremy Lore (Oak Ridge National Laboratory)
    05/06/2017, 11:00
    Divertors and high heat flux components
    Invited Oral

    A set of add-on components referred to as Scraper Elements (SE) were designed as a passive solution to a predicted heat flux overload of certain areas of the main Wendelstein 7-X (W7-X) stellarator divertor during long-pulse operation. W7-X will soon begin its first phase of operation using the first set of plasma facing components (PFCs) and a magnetic topology to realize an island divertor...

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  3. 120. Status of the ITER Cooling Water System Design
    Giovanni Dell'Orco (ITER IO)
    05/06/2017, 11:20
    Divertors and high heat flux components
    Invited Oral

    ITER Cooling Water System (CWS) is designed to reject all the heat generated in the plasma and transmitted to the In-Vessel components through the Tokamak Cooling Water System (TCWS) to the intermediate closed loop Component Cooling Water System (CCWS) and then to the environment via the open Heat Rejection System (HRS).
    The TCWS is designed to remove the total peak heat load of about 1100 MW...

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  4. 173. Virtual Engineering of a fusion reactor: application to divertor design, manufacture and testing
    Dr Thomas R. Barrett (CCFE, Culham Science Centre, Abingdon OX14 3DB, United Kingdom)
    05/06/2017, 11:40
    Divertors and high heat flux components
    Invited Oral

    Owing to ever-growing computational power, Virtual Engineering is transitioning from a possibility to an absolute necessity, and has exciting potential to accelerate the realisation of a fusion power reactor. Virtual Engineering is the use of sophisticated computational modelling to enhance the traditional route of component qualification by providing deeper insight, shortening the design...

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  5. 456. Expermental and numerical investigation on anti-fatigue and anti-thermal shock performance of the divertor first wall
    shenghong Huang (university of science and technology of china)
    05/06/2017, 12:00
    Divertors and high heat flux components
    Oral

    After years of exploration and development, research of magnetic confinement nuclear fusion is progressed into stage of experimental fusion reactor construction and test. As a key plasma-facing component, the anti-fatigue performance of first wall of fusion reactor receives widely concerns. Due to the fact of enduring both periodic loads of pulse operating mode and shock loads of transient...

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