Improved bundle divertor design for ISX-B [electronic resource].
- Published
- Pittsburgh, Pa. : Westinghouse Electric Corporation, 1978.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 30 : digital, PDF file
- Additional Creators
- Westinghouse Electric Corporation and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- The application of Westinghouse's improved bundle divertor design for the ISX-B tokamak at ORNL has been evaluated in detail. The divertor consists of distributed coils with radii increasing outwardly from the plasma plus two auxiliary coils in the vertical plane passing through the center of the divertor and null point of the separatrix. The DITE design that employs nondistributed divertor coils has also been evaluated and compared with the Westinghouse design. There are three major advantages for the Westinghouse design. First, the diverted fluxes are led further away from the plasma and expanded to a larger area; the expansion has been found to be dependent on the divertor coil orientation. Second, the current carried by the divertor coils is reduced and distributed over a larger area; the current density can be reduced by more than a factor of 2. Third, the null points of the separatrices lie approximately on a vertical line instead of on a curve which is convex with respect to the divertor coil. Therefore, more flux can be diverted and uniform shielding could be provided to protect the divertor coil in future reactor applications.
- Report Numbers
- E 1.99:ornl/sub-7117/26
E 1.99: wfps-tme-075
wfps-tme-075
ornl/sub-7117/26 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
02/01/1978.
"ornl/sub-7117/26"
" wfps-tme-075"
Yang, T.F. - Funding Information
- W-7405-ENG-26
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