Next Step Spherical Torus Design Studies Metadata
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Title
- Main Title Next Step Spherical Torus Design Studies
Creator
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Author: Neumeyer, C.Creator Type: Personal
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Author: Heitzenroeder, P.Creator Type: Personal
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Author: Kessel, C.Creator Type: Personal
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Author: Ono, M.Creator Type: Personal
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Author: Peng, M.Creator Type: Personal
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Author: Schmidt, J.Creator Type: Personal
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Author: Woolley, R.Creator Type: Personal
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Author: Zatz, I.Creator Type: Personal
Contributor
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Sponsor: United States. Department of Energy. Office of Science.Contributor Type: OrganizationContributor Info: USDOE Office of Science (SC) (United States)
Publisher
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Name: Princeton University. Plasma Physics Laboratory.Place of Publication: Princeton, New JerseyAdditional Info: Princeton Plasma Physics Laboratory, NJ (United States)
Date
- Creation: 2002-11-08
Language
- English
Description
- Content Description: Studies are underway to identify and characterize a design point for a Next Step Spherical Torus (NSST) experiment. This would be a ''Proof of Performance'' device which would follow and build upon the successes of the National Spherical Torus Experiment (NSTX) a ''Proof of Principle'' device which has operated at PPPL since 1999. With the Decontamination and Decommissioning (D&D) of the Tokamak Fusion Test Reactor (TFTR) nearly completed, the TFTR test cell and facility will soon be available for a device such as NSST. By utilizing the TFTR test cell, NSST can be constructed for a relatively low cost on a short time scale. In addition, while furthering spherical torus (ST) research, this device could achieve modest fusion power gain for short-pulse lengths, a significant step toward future large burning plasma devices now under discussion in the fusion community. The selected design point is Q=2 at HH=1.4, P subscript ''fusion''=60 MW, 5 second pulse, with R subscript ''0''=1.5 m, A=1.6, I subscript ''p''=10vMA, B subscript ''t''=2.6 T, CS flux=16 weber. Most of the research would be conducted in D-D, with a limited D-T campaign during the last years of the program.
- Physical Description: 809 Kilobytes pages
Subject
- Keyword: Decontamination
- STI Subject Categories: 70 Plasma Physics And Fusion Technology
- Keyword: Spherical Torus
- Keyword: Fusion Reactors Design
- Keyword: Nstx Tokamak
- Keyword: Decommissioning
- Keyword: Tftr Tokamak Fusion Reactors Design
- Keyword: Plasma
- Keyword: Performance
- Keyword: Design
Source
- Other Information: PBD: 8 Nov 2002
Collection
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Name: Office of Scientific & Technical Information Technical ReportsCode: OSTI
Institution
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Name: UNT Libraries Government Documents DepartmentCode: UNTGD
Resource Type
- Report
Format
- Text
Identifier
- Report No.: PPPL-3761
- Grant Number: AC02-76CH03073
- DOI: 10.2172/809932
- Office of Scientific & Technical Information Report Number: 809932
- Archival Resource Key: ark:/67531/metadc737344
Note
- Display Note: INIS; OSTI as DE00809932