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

Status of K-DEMO Design Concept Study

5 Jun 2017, 16:00
20m
Salon 3

Salon 3

Invited Oral Next step devices, DEMO, power plants M.OP3: Next Step Devices, DEMO, Power Plants

Speaker

Dr Keeman Kim (National Fusion Research Institure, Republic of Korea)

Description

The conceptual study on the Korean fusion demonstration reactor (K-DEMO) has been carried out since 2012 [1]. K-DEMO is featured by the medium size tokamak (R = 6.8 m, a = 2.1), a high magnetic field (B$_{To}$ = 7.4 T) with steady-state operation. The primary candidate of coolant medium is the pressurized water. One unique aspect of K-DEMO is a two-staged development plan to mitigate the gaps between the present level of technology and the required technology level for the full functions of DEMO. At first, K-DEMO targets not only to demonstrate a net electricity generation (Q$_{eng}$ > 1) and a self-sustained tritium cycle, but also to function as a component test facility. Then, at its second stage, a major upgrade is expected to replace in-vessel components in order to demonstrate a net electric generation on the order of 500 MWe.
A preliminary operating scenario using a combination of various H&CDs (heating and current drives) covering neutral beam, electron cyclotron, lower hybrid, and fast wave H&CDs has been derived. The total H&CD power is estimated approximately 110 MW. The main components of K-DEMO have been conceptualized. The superconducting magnets (toroidal field (TF), poloidal field, and central solenoid magnets) were developed. Key features of the K-DEMO magnet system include the use of two TF coil winding packs, each of a different conductor design, to reduce the construction cost and save the space for the magnet structure material. The CICCs (Cable-In Conduit Conductors) for each type of magnets were fabricated and tested. Divertor is adopting the monoblock-typed tungsten armors with the reference choice of a double-null operation. Solid ceramic pebble typed lithium orthosilicate (Li$_{4}$SiO$_{4}$) was primarily selected for the tritium breeder. Extensive mechanical and neutronic analyses have been carried out to support the developed design concepts and the results are presented.

[1] K. Kim et al., “Design concept of K-DEMO for near-term implementation”, Nuclear Fusion 55 (May 2015) 053027 (9pp).

Eligible for student paper award? No

Authors

Dr Keeman Kim (National Fusion Research Institure, Republic of Korea) Dr Kihak Im (National Fusion Research Institure, Republic of Korea) Dr Sungjin Kwon (NFRI) Jongsung Park (National Fusion Research Institute) Dr Hyoung Chan Kim (NFRI) Dr Jun Ho Yeom (NFRI) Dr George Neilson (PPPL) Dr Charles Kessel (Princeton Plasma Physics Laboratory) Thomas Brown (Princeton Plasma Physics Laboratory, Princeton University) Mr Peter Titus (Princeton Plasma Physics Laboratory) Dr David Mikkelsen (Princeton Plasma Physics Laboratory)

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