DocumentCode
2934968
Title
Advances in the operation of the DIII-D neutral beam computer systems
Author
Phillips, J.C. ; Busath, J.L. ; Penaflor, B.G. ; Piglowski, D. ; Kellman, D.H. ; Chiu, H.K. ; Hong, R.M.
Author_Institution
Gen. Atomics, San Diego, CA, USA
Volume
2
fYear
1997
fDate
6-10 Oct 1997
Firstpage
815
Abstract
The DIII-D neutral beam system routinely provides up to 20 MW of deuterium neutral beam heating in support of experiments on the DIII-D tokamak, and is a critical part of the DIII-D physics experimental program. The four computer systems previously used to control neutral beam operation and data acquisition were designed and implemented in the late 1970´s and used on DIII and DIII-D from 1981-1996. By comparison to modern standards, they had become expensive to maintain, slow and cumbersome, making it difficult to implement improvements. Most critical of all, they were not networked computers. During the 1997 experimental campaign, these systems were replaced with new Unix compliant hardware and, for the most part, commercially available software. This paper describes operational experience with the new neutral beam computer systems, and new advances made possible by using features not previously available. These include retention and access to historical data, an asynchronously fired “rules” base, and a relatively straightforward programming interface. Methods and principles for extending the availability of data beyond the scope of the operator consoles will be discussed
Keywords
Unix; data acquisition; fusion reactor design; fusion reactor ignition; fusion reactor operation; nuclear engineering computing; plasma beam injection heating; plasma toroidal confinement; 0 to 20 MW; D; DIII-D neutral beam computer systems operation; DIII-D tokamak; NBI heating; Unix compliant hardware; data acquisition; fusion reactors; neutral beam heating; programming interface; Computer displays; Computer networks; Control systems; Data acquisition; Hardware; Heating; Plasma displays; Power supplies; Power system reliability; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location
San Diego, CA
Print_ISBN
0-7803-4226-7
Type
conf
DOI
10.1109/FUSION.1997.687750
Filename
687750
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