TPX power systems design overview

Conference · Mon Nov 01 04:00:00 EST 1993

OSTI ID:10192147

Neumeyer, C ^[1]; Bronner, G; Lu, E; Ramakrishnan, S ^[2]; Jackson, M ^[3]

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1. Ebasco Services, Inc., New York, NY (United States)
2. Princeton Univ., NJ (United States). Plasma Physics Lab.
3. Lawrence Livermore National Lab., CA (United States)

The power systems for the Tokamak Physics Experiment (TPX) supply the Toroidal Field (TF). Poloidal Field (PF), Field Error Correction (FEC), and Fast Vertical Position Control (FVPC) coil systems, the Neutral Beam (NB), Ion Cyclotron (IC), Lower Hybrid (LH) and Electron Cyclotron (EC) heating and current drive systems, and all balance of plant loads. Existing equipment from the Tokamak Fusion Test Reactor (TFTR), including the motor-generator (MG) sets and the rectifiers, can be adapted for the supply of the TPX PF systems. A new TF power supply is required. A new substation is required for the heating and current drive systems (NB, IC, LH, and EC). The baseline TPX load can be taken directly from the grid without special provision, whereas if all upgrade options are undertaken, a modest amount of reactive compensation will be required. This paper describes the conceptual design of the power systems, with emphasis on the AC, TF, and PF Systems, and the quench protection of the superconducting coils.

• Research Organization: Princeton Univ., NJ (United States). Plasma Physics Lab.
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 10192147
• Report Number(s): PPPL-CFP--2974; CONF-931018--26; ON: DE94002234
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700440
DESIGN
POWER SUPPLIES
ENERGY STORAGE
POWER SYSTEMS
QUENCHING
SAFETY
SUPERCONDUCTING COILS
TOKAMAK DEVICES