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Title: Divertor research on the DIII-D tokamak

Abstract

In this paper the authors summarize recent progress on DIII-D in developing techniques for divertor power and particle control relevant to next generation tokamaks such as the proposed ITER and TPX devices. Density control and helium removal by divertor pumping have been demonstrated for the first time in high confinement ELMing H-mode discharges ({tau} {approximately} 2 {times} {tau}{sub ITER-89P}) following installation of a divertor cryopumping system. The peak divertor heat flux in similar H-mode discharges has been reduced through production of a radiating mantle with neon or argon puffing (reductions of 3--5). A number of diagnostics have been added to improve the understanding of the physical processes involved. They are now designing modified double-null divertor structures for DIII-D that will provide improved particle control for high-triangularity VH-mode plasmas while at the same time allowing for gas puffing to reduce the divertor heat flux.

Authors:
;  [1];  [2]
  1. Lawrence Livermore National Lab., CA (United States)
  2. General Atomics, San Diego, CA (United States); and others
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States); Oak Ridge National Lab., TN (United States); Sandia National Labs., Albuquerque, NM (United States); California Univ., Los Angeles, CA (United States). Dept. of Physics; California Univ., Los Angeles, CA (United States); Lawrence Livermore National Lab., CA (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10104522
Report Number(s):
GA-A-21851; IAEA-CN-60/A-4-I-2; CONF-940933-21
ON: DE95003942; TRN: AHC29503%%112
DOE Contract Number:  
AC03-89ER51114; AC05-84OR21400; AC04-94AL85000; FG03-89ER51121; FG03-86ER53225; W-7405-ENG-48
Resource Type:
Conference
Resource Relation:
Conference: 15. international conference on plasma physics and controlled nuclear fusion research,Madrid (Spain),26 Sep - 1 Oct 1994; Other Information: PBD: Oct 1994
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DOUBLET-3 DEVICE; DIVERTORS; RESEARCH PROGRAMS; ITER TOKAMAK; TPX DEVICE; H-MODE PLASMA CONFINEMENT; PLASMA DENSITY; HELIUM ASH; CRYOPUMPS; PLASMA SCRAPE-OFF LAYER; PLASMA IMPURITIES; 700420; PLASMA-FACING COMPONENTS

Citation Formats

Hill, D N, Allen, S L, and Brooks, N H. Divertor research on the DIII-D tokamak. United States: N. p., 1994. Web.
Hill, D N, Allen, S L, & Brooks, N H. Divertor research on the DIII-D tokamak. United States.
Hill, D N, Allen, S L, and Brooks, N H. Sat . "Divertor research on the DIII-D tokamak". United States. https://www.osti.gov/servlets/purl/10104522.
@article{osti_10104522,
title = {Divertor research on the DIII-D tokamak},
author = {Hill, D N and Allen, S L and Brooks, N H},
abstractNote = {In this paper the authors summarize recent progress on DIII-D in developing techniques for divertor power and particle control relevant to next generation tokamaks such as the proposed ITER and TPX devices. Density control and helium removal by divertor pumping have been demonstrated for the first time in high confinement ELMing H-mode discharges ({tau} {approximately} 2 {times} {tau}{sub ITER-89P}) following installation of a divertor cryopumping system. The peak divertor heat flux in similar H-mode discharges has been reduced through production of a radiating mantle with neon or argon puffing (reductions of 3--5). A number of diagnostics have been added to improve the understanding of the physical processes involved. They are now designing modified double-null divertor structures for DIII-D that will provide improved particle control for high-triangularity VH-mode plasmas while at the same time allowing for gas puffing to reduce the divertor heat flux.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1994},
month = {10}
}

Conference:
Other availability
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