Author: C. E. Kessel
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 36
Book Description
Plasma Profile and Shape Optimization for the Advanced Tokamak Power Plant, ARIES-AT.
Author: C. E. Kessel
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 36
Book Description
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 36
Book Description
Plasma Profile and Shape Optimization for the Advanced Tokamak Power Plant, ARIES-AT.
Author: C. E. Kessel
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 36
Book Description
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 36
Book Description
Physics Basis for the Advanced Tokamak Fusion Power Plant ARIES-AT.
Shape Optimization for DIII-D Advanced Tokamak Plasmas
Author: C. E. Kessel
Publisher:
ISBN:
Category : Magnetohydrodynamic instabilities
Languages : en
Pages : 4
Book Description
Publisher:
ISBN:
Category : Magnetohydrodynamic instabilities
Languages : en
Pages : 4
Book Description
Fusion Science and Technology
Plasma Shape Optimization for Steady-State Tokamak Development in DIII-D.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 7
Book Description
For a more detailed account of the results summarized here and for references, see C.T. Holcomb et al., Phys. Plasmas 16, 056116 (2009). Advanced tokamak research on DIII-D is focused on developing a high fusion gain, steady-state scenario that would eliminate or greatly reduce the demands on an inductive transformer in future machines. Steady-state operation requires the inductively driven current density (j{sub Ind}) be zero everywhere. Most of the total current I{sub p} is typically from self-driven bootstrap current, with the remainder driven by external noninductive sources, such as neutral beam and radiofrequency current drive. This paper describes an extension of the fully noninductive condition (f{sub NI} ≈ 100%) to ≈0.7 current relaxation times that was achieved by a combination of more available ECCD and new scientific insights. The insights are an optimization of performance through variation of the plasma shape parameter known as squareness ([zeta]) and an optimization of divertor magnetic balance. These optimizations simultaneously improve stability, confinement, and density control. These are each essential for achieving fully noninductive operation.
Publisher:
ISBN:
Category :
Languages : en
Pages : 7
Book Description
For a more detailed account of the results summarized here and for references, see C.T. Holcomb et al., Phys. Plasmas 16, 056116 (2009). Advanced tokamak research on DIII-D is focused on developing a high fusion gain, steady-state scenario that would eliminate or greatly reduce the demands on an inductive transformer in future machines. Steady-state operation requires the inductively driven current density (j{sub Ind}) be zero everywhere. Most of the total current I{sub p} is typically from self-driven bootstrap current, with the remainder driven by external noninductive sources, such as neutral beam and radiofrequency current drive. This paper describes an extension of the fully noninductive condition (f{sub NI} ≈ 100%) to ≈0.7 current relaxation times that was achieved by a combination of more available ECCD and new scientific insights. The insights are an optimization of performance through variation of the plasma shape parameter known as squareness ([zeta]) and an optimization of divertor magnetic balance. These optimizations simultaneously improve stability, confinement, and density control. These are each essential for achieving fully noninductive operation.
Annual Highlights
Author: Princeton University. Plasma Physics Laboratory
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 182
Book Description
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 182
Book Description
Shape Optimization for DIII-D Advanced Tokamak Plasmas
Author: C. E. Kessel
Publisher:
ISBN:
Category : Magnetohydrodynamic instabilities
Languages : en
Pages : 4
Book Description
Publisher:
ISBN:
Category : Magnetohydrodynamic instabilities
Languages : en
Pages : 4
Book Description
Development of a Tokamak Plasma Optimized for Stability and Confinement
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Design of an economically attractive tokamak fusion reactor depends on producing steady-state plasma operation with simultaneous high energy density ([beta]) and high energy confinement ([tau][sub E]); either of these, by itself, is insufficient. In operation of the DIII-D tokamak, both high confinement enhancement (H[equivalent-to][tau][sub E]/[tau][sub ITER-89P]= 4) and high normalized[beta] ([beta][sub N][equivalent-to][beta]/(I/aB)= 6%-m-T/MA) have been obtained. For the present, these conditions have been produced separately and in transient discharges. The DIII-D advanced tokamak development program is directed toward developing an understanding of the characteristics which lead to high stability and confinement, and to use that understanding to demonstrate stationary, high performance operation through active control of the plasma shape and profiles. The authors have identified some of the features of the operating modes in DIII-D that contribute to better performance. These are control of the plasma shape, control of both bulk plasma rotation and shear in the rotation and Er profiles, and particularly control of the toroidal current profiles. In order to guide their future experiments, they are developing optimized scenarios based on their anticipated plasma control capabilities, particularly using fast wave current drive (on-axis) and electron cyclotron current drive (off-axis). The most highly developed model is the second-stable core VH-mode, which has a reversed magnetic shear safety factor profile[q(O)= 3.9, q[sub min]= 2.6, and q[sub 95]= 6]. This model plasma uses profiles which the authors expect to be realizable. At[beta][sub N][>=] 6, it is stable to n=l kink modes and ideal ballooning modes, and is expected to reach H[>=] 3 with VH-mode-like confinement.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Design of an economically attractive tokamak fusion reactor depends on producing steady-state plasma operation with simultaneous high energy density ([beta]) and high energy confinement ([tau][sub E]); either of these, by itself, is insufficient. In operation of the DIII-D tokamak, both high confinement enhancement (H[equivalent-to][tau][sub E]/[tau][sub ITER-89P]= 4) and high normalized[beta] ([beta][sub N][equivalent-to][beta]/(I/aB)= 6%-m-T/MA) have been obtained. For the present, these conditions have been produced separately and in transient discharges. The DIII-D advanced tokamak development program is directed toward developing an understanding of the characteristics which lead to high stability and confinement, and to use that understanding to demonstrate stationary, high performance operation through active control of the plasma shape and profiles. The authors have identified some of the features of the operating modes in DIII-D that contribute to better performance. These are control of the plasma shape, control of both bulk plasma rotation and shear in the rotation and Er profiles, and particularly control of the toroidal current profiles. In order to guide their future experiments, they are developing optimized scenarios based on their anticipated plasma control capabilities, particularly using fast wave current drive (on-axis) and electron cyclotron current drive (off-axis). The most highly developed model is the second-stable core VH-mode, which has a reversed magnetic shear safety factor profile[q(O)= 3.9, q[sub min]= 2.6, and q[sub 95]= 6]. This model plasma uses profiles which the authors expect to be realizable. At[beta][sub N][>=] 6, it is stable to n=l kink modes and ideal ballooning modes, and is expected to reach H[>=] 3 with VH-mode-like confinement.
Fusion Policy
Author: United States. Congress. House. Committee on Science, Space, and Technology. Subcommittee on Energy
Publisher:
ISBN:
Category : Political Science
Languages : en
Pages : 536
Book Description
Distributed to some depository libraries in microfiche.
Publisher:
ISBN:
Category : Political Science
Languages : en
Pages : 536
Book Description
Distributed to some depository libraries in microfiche.