scholarly journals Local Physics Basis of Confinement Degradation in JET ELMy H-Mode Plasmas and Implications for Tokamak Reactors

2001 ◽  
Author(s):  
R.V. Budny ◽  
B. Alper ◽  
D. Borba ◽  
J.G. Cordey ◽  
D.R. Ernst ◽  
...  
Keyword(s):  
Tokamak Reactors

Buckling of a Superconducting Ring in a Toroidal Magnetic Field

1979 ◽  
Vol 46 (1) ◽  
pp. 151-155 ◽  
Author(s):  
F. C. Moon
Keyword(s):  
Magnetic Field ◽  
Theoretical Model ◽  
Toroidal Magnetic Field ◽  
Magnetic Fusion ◽  
Poloidal Field ◽  
Superconducting Ring ◽  
Tokamak Reactors ◽  
Linear And Nonlinear ◽  
Mode A ◽  
Theory And Experiment

Experimental evidence and a theoretical model are presented for the magnetoelastic buckling of a rigid superconducting ring in a steady circumferential (toroidal)magnetic field. The theoretical model predicts a coupled translation and pitch displacement of the coil in the buckled mode. A discussion is given of both the linear and nonlinear magnetic perturbation forces. The experiments were conducted in liquid helium (4.2°K). The lowest natural frequency of the rigid coil on elastic springs was observed to decrease near the buckling current. Agreement between theory and experiment is fair. These results may have design implications for poloidal field coils in magnetic fusion Tokamak reactors.

Plasma power balance models for self-sustained tokamak reactors

1977 ◽  
Vol 17 (5) ◽  
pp. 955-968 ◽  
Author(s):  
E. Bertolini ◽  
F. Engelmann ◽  
M.A. Hoffman ◽  
A. Taroni
Keyword(s):  
Power Balance ◽  
Plasma Power ◽  
Tokamak Reactors

scholarly journals Neutral-beam energy and power requirements for expanding-radius and full-bore start-up of tokamak reactors

1980 ◽  
Vol 20 (7) ◽  
pp. 811-820 ◽  
Author(s):  
W.A. Houlberg ◽  
S.E. Attenberger ◽  
A.T. Mense
Keyword(s):  
Beam Energy ◽  
Neutral Beam ◽  
Start Up ◽  
Tokamak Reactors

Design and simulation of a blanket module for TOKAMAK reactors

2019 ◽  
Vol 34 (13) ◽  
pp. 1950103 ◽  
Author(s):  
H. Sadeghi ◽  
M. Habibi
Keyword(s):  
Comsol Multiphysics ◽  
Fusion Reactors ◽  
Tritium Breeding ◽  
Mcnpx Code ◽  
Self Sufficiency ◽  
Proposed Model ◽  
Tokamak Reactors ◽  
Breeding Ratio ◽  
Neutron Multiplier ◽  
Temperature And Pressure

In this paper, we simulated an appropriate model for an advanced breeding blanket of future TOKAMAK fusion reactors with solid breeder (Li4SiO4) building material in the form of pebble beds, ODS ferritic steel as structural material and Beryllium as neutron multiplier. With the MCNPX code, the efficiency of this proposed model for the production and self-sufficiency of tritium was investigated. Total tritium breeding ratio of 1.15 is achieved. The helium-cooled pebble bed system and parameters of temperature and pressure are investigated by COMSOL multiphysics simulating software. The temperature of helium as cooling gas never exceeded 530[Formula: see text]C and the tolerable temperature of beryllium was obtained at 650[Formula: see text]C. In the proposed design, it is adequate to enrich the 6Li to 40%.

Neutron wall loading of Tokamak reactors

2000 ◽  
Vol 283-287 ◽  
pp. 588-592 ◽  
Author(s):  
C.P.C. Wong
Keyword(s):  
Tokamak Reactors ◽  
Wall Loading
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