Affordable Access

The conceptual design for the modification of HL-2A tokamak

Authors
Journal
Fusion Engineering and Design
0920-3796
Publisher
Elsevier
Publication Date
Volume
82
Identifiers
DOI: 10.1016/j.fusengdes.2007.05.059
Keywords
  • Hl-2A Tokamak
  • Modification
  • Configuration

Abstract

Abstract HL-2A has achieved parameters of I p = 400 kA, B t = 2.65 T, approaching to its rated operational parameters with I p = 450 kA and B t = 2.8 T so far. Considering present status of HL-2A tokamak and in order to extend experimental research further, the HL-2A will be modified with a more efficient divertor. The objective of modification of HL-2A is to obtain optimized plasma parameters and shape, and an advanced divertor. The plasma configuration will be realized by composite arranging of poloidal field coil (PFC) system. After modification, the plasma current I p will reach 800 kA, the elongation and triangularity of plasma will be above 1.6 and 0.3, respectively.

There are no comments yet on this publication. Be the first to share your thoughts.

Statistics

Seen <100 times
0 Comments

More articles like this

Divertor design for HL-2A tokamak modification

on Journal of Nuclear Materials Aug 01, 2011

Part I Conceptual design of the R-tokamak

on Fusion Engineering and Design Jan 01, 1987
More articles like this..