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Oct 13 – 18, 2014
Hotel Park Inn Pribaltiyskaya
Europe/Moscow timezone

Availability Considerations in the Design of K-DEMO

Oct 17, 2014, 8:30 AM
4h
Green 8-9 (Hotel Park Inn Pribaltiyskaya)

Green 8-9

Hotel Park Inn Pribaltiyskaya

Saint Petersburg, Russian Federation
Poster Poster 7

Speaker

Dr Keeman Kim (Korea, Republic of)

Description

A DEMO device has been considered the next step following ITER as a near-term prototypical reactor design that is tritium self-sufficient and produces a limited amount of net electricity. The machine maintenance approach and planned configuration concept plays a major role in establishing the design point. DEMO will also need to show that adequate operating availability can be achieved over a reasonable time period, as a last step before full-scale electricity production. The ability to operate with high availability/reliability plays a key ingredient in defining the DEMO configuration, fostering the need for rapid removal/replacement of limited-life in-vessel components. DEMO pre-conceptual studies are being carried out by China, EU, Japan and South Korea (with US participation). The device designs span a range of maintenance approaches from full radial extraction of large in-vessel modules through all TF horizontal openings to vertical maintenance of segmented in-vessel components. Progress made on the S. Korea’s K-DEMO design will be provided with emphasis on the design choices identified to promote high availability and a review of how these design selections compare with the choices made on the Chinese, EU and Japan concepts.
Paper Number FIP/P7-1
Country or International Organisation USA

Primary author

Mr Thomas Brown (Princeton University, Princeton Plasma Physics Laboratory)

Co-authors

Dr Charles Kessel (Princeton Plasma Physics Laboratory) Dr George Neilson (Princeton Plasma Physics Laboratory) Dr Jong Sung Park (2National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, the Republic of Korea) Dr Keeman Kim (Korea, Republic of) Dr Kihak Im (2National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, the Republic of Korea) Dr Peter Titus (Princeton Plasma Physics Lab, Princeton University)

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