Published October 2011 | Version v1
Journal article

Development of KSTAR in-vessel components and heating systems

  • 1. National Fusion Research Institute, Daejeon (Korea, Republic of)
  • 2. Pohang University of Science and Technology, Pohang (Korea, Republic of)

Description

In-vessel components of the Korea Superconducting Tokamak Advanced Research (KSTAR) were developed for 2010 campaign to provide a crucial circumstance for achieving the strongly shaped and diverted plasma. Moreover, the in-vessel components such as limiter, divertor, passive stabilizer, in-vessel control coil (IVCC) system demonstrated good performances satisfying the original design concepts. In addition to the plasma facing components and the IVCC, in-vessel cryo-pump (IVCP) system was also installed to leverage divertor operation. Besides the in-vessel components, there have been substantial progresses in development of the heating and current drive system. The KSTAR heating and current drive system includes all kinds of the major heating systems such as neutral beam injection (NBI), ion cyclotron range of frequency (ICRF), electron cyclotron resonance heating and current drive (ECH and ECCD), lower hybrid current drive (LHCD) systems. As an initial stage for full equipment of the heating systems to total power of 26 MW, several key systems such as 1st NBI (called NBI-1), ICRF, and ECH-assisted startup system successfully demonstrated their excellent feasibilities in the design and performances for dedication to the 2010 campaign.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2011.02.083

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2011.02.083;
PII
S0920-3796(11)00253-5;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
86
Journal Issue
6-8
Journal Page Range
p. 588-592
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
26. symposium on fusion technology
Acronym
SOFT-26
Dates
27 Sep - 1 Oct 2010
Place
Porto (Portugal)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43065257
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIVERTORS; ECR CURRENT DRIVE; ECR HEATING; FIRST WALL; HEATING SYSTEMS; LIMITERS; LOWER HYBRID CURRENT DRIVE; NEUTRAL ATOM BEAM INJECTION; PUMPS; TOKAMAK DEVICES
Descriptors DEC
BEAM INJECTION; CLOSED PLASMA DEVICES; ENERGY SYSTEMS; EQUIPMENT; HEATING; HIGH-FREQUENCY HEATING; NON-INDUCTIVE CURRENT DRIVE; PLASMA HEATING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.