SLPX: superconducting long-pulse experiment
Conference
·
OSTI ID:6412629
The principal objectives of the SLPX--Superconducting Long-Pulse Experiment--are to demonstrate quasi-steady operation of 3 to 5 MA hydrogen and deuterium plasmas at high temperature and high thermal wall loading, and to develop reliable operation of a prototypical reactor magnetics systems featuring a toroidal assembly of high-field niobium-tin coils. This report summarizes the results of an engineering scoping study for the SLPX. A range of sizes has been investigated, from a TF (toroidal-field) coil aperture of 2.6 m x 3.65 m, to an aperture of 3.1 m x 4.8 m, and with a maximum field at the Nb/sub 3/Sn conductor of 10 to 12 Tesla. The poloidal-field magnetics system utilizes superconducting ohmic-heating and d.c. EF coils located outside the TF coils, together with normal-conducting EF and divertor coils located inside the TF coils. For the largest embodiment, the D-shaped plasma in hydrogen operation has major radius = 3.6 m, half-width = 0.90 m, elongation < 1.5, and B = 7,2 T. Maximum plasma current of 5.0 MA can be maintained for a 30-s flat-top when Z/sub eff/approximately 1. A single-null poloidal magnetic divertor disposes of particles and heat diffusing out of the current channel, thereby helping to insure the feasibility of quasi-steady operation.
- Research Organization:
- Princeton Univ., NJ (USA). Plasma Physics Lab.
- DOE Contract Number:
- EY-76-C-02-3073
- OSTI ID:
- 6412629
- Report Number(s):
- PPPL-1481; CONF-780966-1
- Country of Publication:
- United States
- Language:
- English
Similar Records
SLPX: superconducting long-pulse tokamak experiment. [NbTi]
The superconducting magnet system for the Tokamak Physics Experiment
Ripple reduction coils for tokamak reactors
Conference
·
Mon Sep 25 00:00:00 EDT 1978
·
OSTI ID:6439724
The superconducting magnet system for the Tokamak Physics Experiment
Conference
·
Sat Jun 18 00:00:00 EDT 1994
·
OSTI ID:10180297
Ripple reduction coils for tokamak reactors
Technical Report
·
Sun Mar 27 23:00:00 EST 1983
·
OSTI ID:6334575
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
ALLOYS
CLOSED PLASMA DEVICES
CRYOGENIC FLUIDS
DESIGN
DEUTERIUM
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ELEMENTS
EQUIPMENT
FLUIDS
HYDROGEN
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAGNETS
NIOBIUM ALLOYS
NIOBIUM BASE ALLOYS
NONMETALS
NUCLEI
ODD-ODD NUCLEI
POWER DENSITY
PULSES
STABLE ISOTOPES
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR DEVICES
TIME DEPENDENCE
TIN ALLOYS
TOKAMAK DEVICES
WALL LOADING
700200* -- Fusion Energy-- Fusion Power Plant Technology
ALLOYS
CLOSED PLASMA DEVICES
CRYOGENIC FLUIDS
DESIGN
DEUTERIUM
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ELEMENTS
EQUIPMENT
FLUIDS
HYDROGEN
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAGNETS
NIOBIUM ALLOYS
NIOBIUM BASE ALLOYS
NONMETALS
NUCLEI
ODD-ODD NUCLEI
POWER DENSITY
PULSES
STABLE ISOTOPES
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR DEVICES
TIME DEPENDENCE
TIN ALLOYS
TOKAMAK DEVICES
WALL LOADING