Published March 22, 2000
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The importance of the toroidal magnetic field for the feasibility of a tokamak burning plasma experiment
Description
The next step in the demonstration of the scientific feasibility of a tokamak fusion reactor is a DT burning plasma experiment for the study and control of self-heated plasmas. In this paper, the authors examine the role of the toroidal magnetic field on the confinement of a tokamak plasma in the ELMy H-mode regime--the operational regime foreseen for ITER
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00752525; PURL: https://www.osti.gov/servlets/purl/752525-qsMgkn/webviewable/
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- PPPL--3442
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 31031783
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- D-T OPERATION; EDGE LOCALIZED MODES; ENERGY BALANCE; FEASIBILITY STUDIES; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; MAGNETIC FIELDS
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; INSTABILITY; MAGNETIC CONFINEMENT; PLASMA CONFINEMENT; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Contract/Grant/Project number
- AC02-76CH03073
- Funding organization
- USDOE Office of Energy Research (ER) (United States)