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Title: The engineering design of TPX

Conference ·
OSTI ID:10192145

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 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 and poloidal field magnets. 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 Project and describes the design approach with emphasis on salient features of the tokamak.

Research Organization:
Princeton Univ., NJ (United States). Plasma Physics Lab.
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC02-76CH03073
OSTI ID:
10192145
Report Number(s):
PPPL-CFP-2975; CONF-931018-25; ON: DE94002235; TRN: 93:024171
Resource Relation:
Conference: Symposium on fusion engineering,Hyannis, MA (United States),11-15 Oct 1993; Other Information: PBD: [1993]
Country of Publication:
United States
Language:
English

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