Conceptual analysis and design of NSTX vacuum vessel and support structures
- Princeton Plasma Physics Lab., NJ (United States)
The National Spherical Tokamak Experiment is a low-aspect-ratio tokamak facility currently in the conceptual design phase. The vacuum vessel, in addition to provides a high vacuum chamber for plasma experiments, also serves as a load-carrying element for supporting the center stack, the external poloidal field coils, and the toroidal field coils. Design requirements and structural considerations for the vacuum vessel and its support structure were described in the paper. Structural responses were calculated using the finite element method. Various loading conditions including in the analyses are dead weight, static electromagnetic loads, plasma disruptions, bakeout thermal effects, vacuum pressure, seismic excitations, and simultaneously occurrence of such loadings.
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 465030
- Report Number(s):
- CONF-950905-; ISBN 0-7803-2969-4; TRN: 97:007538
- Resource Relation:
- Conference: 16. IEEE/NPSS symposium on fusion engineering, Champaign, IL (United States), 1-5 Oct 1995; Other Information: PBD: 1995; Related Information: Is Part Of 1995 IEEE 16. symposium on fusion engineering. Volume 2; Miley, G.H.; Elliott, C. [eds.] [Univ. of Illinois, Urbana, IL (United States). Fusion Studies Lab.]; PB: 851 p.
- Country of Publication:
- United States
- Language:
- English
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