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Physics of Compact Ignition Tokamak Designs

Physics of Compact Ignition Tokamak Designs PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 39

Book Description


Physics of Compact Ignition Tokamak Designs

Physics of Compact Ignition Tokamak Designs PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 39

Book Description


Ignition Probabilities for Compact Ignition Tokamak Designs

Ignition Probabilities for Compact Ignition Tokamak Designs PDF Author: D. P. Stotler
Publisher:
ISBN:
Category :
Languages : en
Pages : 46

Book Description


Physics Aspects of the Compact Ignition Tokamak

Physics Aspects of the Compact Ignition Tokamak PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 70

Book Description


Pulse Length Assessment of Compact Ignition Tokamak Designs

Pulse Length Assessment of Compact Ignition Tokamak Designs PDF Author: D. P. Stotler
Publisher:
ISBN:
Category :
Languages : en
Pages : 31

Book Description


Physics Aspects of the Compact Ignition Tokamak

Physics Aspects of the Compact Ignition Tokamak PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The Compact Ignition Tokamak (CIT) is a proposed modest-size ignition experiment designed to study the physics of alpha-particle heating. The basic concept is to achieve ignition in a modest-size minimum cost experiment by using a high plasma density to achieve the condition of ntau/sub E/ approx. 2 x 102° sec m−3 required for ignition. The high density requires a high toroidal field (10 T). The high toroidal field allows a large plasma current (10 MA) which improves the energy confinement, and provides a high level of ohmic heating. The present CIT design also has a gigh degree of elongation (k approx. 1.8) to aid in producing the large plasma current. A double null poloidal divertor and a pellet injector are part of the design to provide impurity and particle control, improve the confinement, and provide flexibility for impurity and particle control, improve the confinement, and provide flexibility for improving the plasma profiles. Since auxiliary heating is expected to be necessary to achieve ignition, 10 to 20 MW of Ion Cyclotron Radio Frequency (ICRF) is to be provided.

"Crescent"-shaped Tokamak for Compact Ignition

Author: K. Yamazaki
Publisher:
ISBN:
Category : Nuclear fusion
Languages : en
Pages : 22

Book Description


Simulation of a Compact Ignition Tokamak

Simulation of a Compact Ignition Tokamak PDF Author: Glenn Bateman
Publisher:
ISBN:
Category :
Languages : en
Pages : 25

Book Description


Pulse Length Assessment of Compact Ignition Tokamak Designs

Pulse Length Assessment of Compact Ignition Tokamak Designs PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
A time-dependent zero-dimensional code has been developed to assess the pulse length and auxiliary heating requirements of Compact Ignition Tokamak (CIT) designs. By taking a global approach to the calculation, parametric studies can be easily performed. The accuracy of the procedure is tested by comparing with the Tokamak Simulation Code which uses theory-based thermal diffusivities. A series of runs is carried out at various levels of energy confinement for each of three possible CIT configurations. It is found that for cases of interest, ignition or an energy multiplication factor Q /approx gt/ 7 can be attained within the first half of the planned five-second flattop with 10--40 MW of auxiliary heating. These results are supported by analytic calculations. 18 refs., 7 figs., 2 tabs.

Time-dependent Simulations of a Compact Ignition Tokamak

Time-dependent Simulations of a Compact Ignition Tokamak PDF Author: D. P. Stotler
Publisher:
ISBN:
Category :
Languages : en
Pages : 54

Book Description


Physics Guidelines for the Compact Ignition Tokamak

Physics Guidelines for the Compact Ignition Tokamak PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The goal of the Compact Ignition Tokamak (CIT)d program is to provide a cost-effective route to the production of a burning deuterium-tritium plasma, so that alpha-particle effects may be studied. A key issue to be studied in the CIT is whether alpha power behaves like other power sources in affecting tokamak plasma confinement. The program is managed by the Princeton Physics Laboratory and includes broad community involvement. Guidelines for the preliminary design effort have been provided by the Ignition Technical Oversight Committee in discussion with the tokamak community. The reference design is a tokamak with a high filed (10 T), high current (10 MA), poloidal divertor, and liquid-nitrogen-cooled coils. It is a small, high-power-density device of the type proposed by Bruno Coppi (MIT). It has a major radius of 1.23 m, a minor radius of 0.43 m, and plasma elipticity of 1.8. This paper reviews the aims of the program and the basis for the physics guidelines. The role of the CIT in the longer-term tokamak program is briefly discussed. 23 refs., 9 figs., 1 tab.