Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Most of the components of the Neutral Beam Lines of the Tokamak Fusion Test Reactor (TFTR) will be enclosed in a 50 cubic meter box-shaped vacuum chamber. The chamber will have a number of unorthodox features to accomodate both neutral beam and TFTR requirements. The design constraints, and the resulting chamber design, are presented.
Tokamak Fusion Test Reactor Neutral Beam Injection System Vacuum Chamber
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Most of the components of the Neutral Beam Lines of the Tokamak Fusion Test Reactor (TFTR) will be enclosed in a 50 cubic meter box-shaped vacuum chamber. The chamber will have a number of unorthodox features to accomodate both neutral beam and TFTR requirements. The design constraints, and the resulting chamber design, are presented.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Most of the components of the Neutral Beam Lines of the Tokamak Fusion Test Reactor (TFTR) will be enclosed in a 50 cubic meter box-shaped vacuum chamber. The chamber will have a number of unorthodox features to accomodate both neutral beam and TFTR requirements. The design constraints, and the resulting chamber design, are presented.
Tokamak Fusion Test Reactor (TFTR) Neutral Beam Line Vacuum Chamber Cover Structural Analysis
Neutral Beam Injection System for the Tokamak Fusion Test Reactor
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facility. This is a major step to reach the goal of fusion power using toroidal magnetic fields for plasma confinement. A major part of this test reactor will be four neutral beam injection systems. These systems will inject 20 MW of 120 kV neutral deuterium atoms into the plasma for 0.5 seconds. In order to achieve the required power input to the plasma, several systems are required within the neutral beam line. These are the source, neutralizer, ion deflection magnet, calorimeter and retraction system, ion dump, cryopumps and vacuum enclosure. All of these systems have constraints imposed which increase the complexity of their designs. Since all systems must operate in a tritium environment, remote handling capabilities must be incorporated into the design. An overview is presented of the Lawrence Livermore Laboratory/Lawrence Berkeley Laboratory Neutral Beam Injection System design. Specifications for the machine and a general description of the total system are presented.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facility. This is a major step to reach the goal of fusion power using toroidal magnetic fields for plasma confinement. A major part of this test reactor will be four neutral beam injection systems. These systems will inject 20 MW of 120 kV neutral deuterium atoms into the plasma for 0.5 seconds. In order to achieve the required power input to the plasma, several systems are required within the neutral beam line. These are the source, neutralizer, ion deflection magnet, calorimeter and retraction system, ion dump, cryopumps and vacuum enclosure. All of these systems have constraints imposed which increase the complexity of their designs. Since all systems must operate in a tritium environment, remote handling capabilities must be incorporated into the design. An overview is presented of the Lawrence Livermore Laboratory/Lawrence Berkeley Laboratory Neutral Beam Injection System design. Specifications for the machine and a general description of the total system are presented.
Tokamak Fusion Test Reactor
Author: Princeton University. Plasma Physics Laboratory
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 8
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 8
Book Description
Fusion Energy Update
Energy Research Abstracts
Fusion Energy, an Overview of the Magnetic Confinement Approach, Its Objectives, and Pace
Vacuum for a Tokamak Experimental Fusion Power Reactor
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A preliminary study was made of the vacuum system requirements for a D-T burning TEPR with major radius R = 6.25 m and plasma radius a = 2.1 m. Approximate requirements for the neutral injector vacuum system have been determined as functions of neutral beam power for a one-component, 180 keV D$sup 0$ beam derived from D. For the 40 MW reference design DĀ° beam, the total injector gas load varies from approximately 500 to approximately 800 Torr-l/ s as the assumed ion source gas efficiency varies from 40 to 25 percent. The torus or plasma containment vessel has 711 m3 of volume and 592 m2 of surface area. Material selection for the first wall will affect the total gas load available to be pumped. The toroidal pumping system must be able to reduce the pressure after the burn or fusion cycle from 10ā3 Torr to 10ā5 Torr or less in 10 to 15 s. Furthermore, before each experimental run, or possibly more often, this pumping system must be capable of evacuating the entire volume down to 1 x 10ā8 Torr or less to assure a reasonably contamination free plasma. (auth).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A preliminary study was made of the vacuum system requirements for a D-T burning TEPR with major radius R = 6.25 m and plasma radius a = 2.1 m. Approximate requirements for the neutral injector vacuum system have been determined as functions of neutral beam power for a one-component, 180 keV D$sup 0$ beam derived from D. For the 40 MW reference design DĀ° beam, the total injector gas load varies from approximately 500 to approximately 800 Torr-l/ s as the assumed ion source gas efficiency varies from 40 to 25 percent. The torus or plasma containment vessel has 711 m3 of volume and 592 m2 of surface area. Material selection for the first wall will affect the total gas load available to be pumped. The toroidal pumping system must be able to reduce the pressure after the burn or fusion cycle from 10ā3 Torr to 10ā5 Torr or less in 10 to 15 s. Furthermore, before each experimental run, or possibly more often, this pumping system must be capable of evacuating the entire volume down to 1 x 10ā8 Torr or less to assure a reasonably contamination free plasma. (auth).