Recent results from the DIII-D tokamak

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The DIII-D national fusion research program focuses on establishing the scientific basis for optimization of the tokamak approach to fusion energy production. The symbiotic development of research, theory, and hardware continues to fuel the success of the DIII-D program. During the last year, a radiative divertor and a second cryopump were installed in the DIII-D vacuum vessel, an array of central and boundary diagnostics were added, and more sophisticated computer models were developed. These new tools have led to substantial progress in the understanding of the plasma. The authors now have a better understanding of the divertor as a means ... continued below

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11 p.

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Petersen, P.I. February 1, 1998.

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  • General Atomic Company
    Publisher Info: General Atomics, San Diego, CA (United States)
    Place of Publication: San Diego, California

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The DIII-D national fusion research program focuses on establishing the scientific basis for optimization of the tokamak approach to fusion energy production. The symbiotic development of research, theory, and hardware continues to fuel the success of the DIII-D program. During the last year, a radiative divertor and a second cryopump were installed in the DIII-D vacuum vessel, an array of central and boundary diagnostics were added, and more sophisticated computer models were developed. These new tools have led to substantial progress in the understanding of the plasma. The authors now have a better understanding of the divertor as a means to manage the heat, particle, and impurity transport pumping of the plasma edge using the in situ divertor cryopumps effectively controls the plasma density. The evolution of diagnostics that probe the interior of the plasma, particularly the motional Stark effect diagnostic, has led to a better understanding of the core of the plasma. This understanding, together with tools to control the profiles, including electron cyclotron waves, pellet injection, and neutral beam injection, has allowed them to progress in making plasma configurations that give rise to both low energy transport and improved stability. Most significant here is the use of transport barriers to improve ion confinement to neoclassical values. Commissioning of the first high power (890 kW) 110 GHz gyrotron validates an important tool for managing the plasma current profile, key to maintaining the transport barriers. An upgraded plasma control system, ``isoflux control,`` which exploits real time MHD equilibrium calculations to determine magnetic flux at specified locations within the tokamak vessel and provides the means for precisely controlling the plasma shape and, in conjunction with other heating and fueling systems, internal profiles.

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11 p.

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INIS; OSTI as DE98003428

Source

  • 17. IEEE/NPSS symposium on fusion engineering, San Diego, CA (United States), 6-10 Oct 1997

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  • Other: DE98003428
  • Report No.: GA--A22748
  • Report No.: CONF-971065--
  • Grant Number: AC03-89ER51114
  • Office of Scientific & Technical Information Report Number: 645537
  • Archival Resource Key: ark:/67531/metadc696353

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Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • February 1, 1998

Added to The UNT Digital Library

  • Aug. 14, 2015, 8:43 a.m.

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  • April 18, 2016, 6:03 p.m.

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Petersen, P.I. Recent results from the DIII-D tokamak, article, February 1, 1998; San Diego, California. (digital.library.unt.edu/ark:/67531/metadc696353/: accessed April 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.