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Title: Magnetic configuration flexibility of snowflake divertor for HL-2M [Analysis of snowflake divertor configurations for HL-2M]

Journal Article · · Fusion Engineering and Design
 [1];  [2];  [2];  [3];  [4]
  1. Southwestern Institute of Physics, Chengdu (People's Republic of China); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  3. Southwestern Institute of Physics, Chengdu (People's Republic of China)
  4. Chinese Academy of Sciences, Hefei (People's Republic of China)

HL-2M (Li, 2013 [1]) is a tokamak device that is under construction. Based on the magnetic coils design of HL-2M, four kinds of divertor configurations are calculated by CORSICA code (Pearlstein et al., 2001 [2]) with the same main plasma parameters, which are standard divertor, exact snowflake divertor, snowflake-plus divertor and snowflake-minus divertor configurations. The potential properties of these divertors are analyzed and presented in this paper: low poloidal field area around X-point, connection length from outside mid-plane to the primary X-point, target plate design and magnetic field shear. The results show that the snowflake configurations not only can reduce the heat load at divertor target plates, but also may improve the magneto-hydrodynamic stability by stronger magnetic shear at the edge. Furthermore, a new divertor configuration, named “tripod divertor”, is designed by adjusting the positions of the two X-points according to plasma parameters and magnetic coils current of HL-2M.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC52-07NA27344
OSTI ID:
1313554
Report Number(s):
LLNL-JRNL-651522
Journal Information:
Fusion Engineering and Design, Vol. 89, Issue 11; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 14 works
Citation information provided by
Web of Science

References (14)

The physics of the International Thermonuclear Experimental Reactor FEAT journal May 2001
Overview of physics basis for ITER journal November 2003
Conceptual design study of fusion DEMO plant at SWIP journal December 2009
Simulation study for divertor design to handle huge exhaust power in the SlimCS DEMO reactor journal May 2009
The super X divertor (SXD) and a compact fusion neutron source (CFNS) journal February 2010
Guidance of Divertor Channel by Cusp-Like Magnetic Field for Tokamak Devices journal March 2001
On heat loading, novel divertors, and fusion reactors journal July 2007
Super-X divertors and high power density fusion devices journal May 2009
Geometrical properties of a “snowflake” divertor journal June 2007
Local properties of the magnetic field in a snowflake divertor journal August 2010
A snowflake divertor: a possible solution to the power exhaust problem for tokamaks journal November 2012
Power exhaust in the snowflake divertor for L- and H-mode TCV tokamak plasmas journal February 2014
Linear peeling–ballooning mode simulations in snowflake-like divertor configuration using BOUT++ code journal February 2014
Edge Plasma in Snowflake Divertor journal May 2010

Cited By (2)

Summary of magnetic fusion plasma physics in 1st AAPPS-DPP meeting journal March 2018
The snowflake divertor journal November 2015

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