The engineering design of the Tokamak Physics Experiment (TPX)
Conference
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OSTI ID:10182057
The Tokamak Physics Experiment (TPX) is designed to develop the scientific basis for a compact and continuously operating tokamak fusion reactor. TPX has a long pulse (1000s) capability, can accommodate high divertor heat loads, has a flexible poloidal field (PF) system, and auxiliary heating and current drive systems that make it an ideal test bed for development of attractive reactor concepts. The design incorporates superconducting magnets in both the toroidal field (TF) and poloidal field (PF) systems. Long pulse deuterium operation will produce 6 {times} 10{sup 21} neutrons per year requiring remote maintenance of the in-vessel hardware. This paper provides an overview of the TPX design with the emphasis on developments in the tokamak design since the Conceptual Design Review (CDR) in March, 1993.
- Research Organization:
- Princeton Univ., NJ (United States). Plasma Physics Lab.
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 10182057
- Report Number(s):
- PPPL-CFP--3152; CONF-940843--6; ON: DE94018343
- Country of Publication:
- United States
- Language:
- English
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