Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The reactor potential of some advanced physics operating modes proposed for the TPX physics program are examined. A moderate aspect ratio (A = 4.5 as in TPX), 2 GW reactor is analyzed because of its potential for steady-state, non-inductive operation with high bootstrap current fraction. Particle, energy and toroidal current equations are evolved to steady-state conditions using the 1-1/2-D time-dependent WHIST transport code. The solutions are therefore consistent with particle, energy and current sources and assumed transport models. Fast wave current drive (FWCD) provides the axial seed current. The bootstrap current typically provides 80-90% of the current, while feedback on the lower hybrid current drive (LHCD) power maintains the total current. The sensitivity of the plasma power amplification factor, Q [equivalent-to] P[sub fus]/P[sub aux], to variations in the plasma properties is examined. The auxiliary current drive power, P[sub aux] = P[sub LH] + P[sub FW]; bootstrap current fraction: current drive efficiency; and other parameters are evaluated. The plasma is thermodynamically stable for the energy confinement model assumed (a multiple of ITER89P). The FWCD and LHCD sources provide attractive control possibilities, not only for the current profile, but also for the total fusion power since the gain on the incremental auxiliary power is typically 10-30 in these calculations when overall Q [approx] 30.
Evaluation of Current Drive Requirements and Operating Characteristics of a High Bootstrap Fraction Advanced Tokamak Reactor
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The reactor potential of some advanced physics operating modes proposed for the TPX physics program are examined. A moderate aspect ratio (A = 4.5 as in TPX), 2 GW reactor is analyzed because of its potential for steady-state, non-inductive operation with high bootstrap current fraction. Particle, energy and toroidal current equations are evolved to steady-state conditions using the 1-1/2-D time-dependent WHIST transport code. The solutions are therefore consistent with particle, energy and current sources and assumed transport models. Fast wave current drive (FWCD) provides the axial seed current. The bootstrap current typically provides 80-90% of the current, while feedback on the lower hybrid current drive (LHCD) power maintains the total current. The sensitivity of the plasma power amplification factor, Q [equivalent-to] P[sub fus]/P[sub aux], to variations in the plasma properties is examined. The auxiliary current drive power, P[sub aux] = P[sub LH] + P[sub FW]; bootstrap current fraction: current drive efficiency; and other parameters are evaluated. The plasma is thermodynamically stable for the energy confinement model assumed (a multiple of ITER89P). The FWCD and LHCD sources provide attractive control possibilities, not only for the current profile, but also for the total fusion power since the gain on the incremental auxiliary power is typically 10-30 in these calculations when overall Q [approx] 30.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The reactor potential of some advanced physics operating modes proposed for the TPX physics program are examined. A moderate aspect ratio (A = 4.5 as in TPX), 2 GW reactor is analyzed because of its potential for steady-state, non-inductive operation with high bootstrap current fraction. Particle, energy and toroidal current equations are evolved to steady-state conditions using the 1-1/2-D time-dependent WHIST transport code. The solutions are therefore consistent with particle, energy and current sources and assumed transport models. Fast wave current drive (FWCD) provides the axial seed current. The bootstrap current typically provides 80-90% of the current, while feedback on the lower hybrid current drive (LHCD) power maintains the total current. The sensitivity of the plasma power amplification factor, Q [equivalent-to] P[sub fus]/P[sub aux], to variations in the plasma properties is examined. The auxiliary current drive power, P[sub aux] = P[sub LH] + P[sub FW]; bootstrap current fraction: current drive efficiency; and other parameters are evaluated. The plasma is thermodynamically stable for the energy confinement model assumed (a multiple of ITER89P). The FWCD and LHCD sources provide attractive control possibilities, not only for the current profile, but also for the total fusion power since the gain on the incremental auxiliary power is typically 10-30 in these calculations when overall Q [approx] 30.
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 602
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 602
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
INIS Atomindex
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 730
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 730
Book Description
Fusion Technology
Author:
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 1076
Book Description
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 1076
Book Description
Proceedings of the Fourteenth Topical Meeting on the Technology of Fusion Energy, October 15-19, 2000, Park City, Utah
Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 906
Book Description
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 906
Book Description
Proceedings of the Thirteenth Topical Meeting on the Technology of Fusion Energy
Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 1074
Book Description
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 1074
Book Description
Maximal Bootstrap Current Tokamak Equilibria in the First Stability Regime
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A series of tokamak equilibria are studied in order to identify characteristics which may maximize the proportion of toroidal current naturally provided by the bootstrap effect. These plasmas are typical of high field reactors considered by the ARIES (Advanced Reactor Innovation and Evaluation Study) collaboration and are assumed to have rather flat density profiles and broad pressure profiles. With the use of noninductive current drive to provide the seed current it is possible to operate with q/sub axis/ approx. = 2.0; this results in a (bootstrap-assissted) current drive power of P/sup B//sub CD/ - 117 MW and a figure of merit /sub gamma//sup B/ = 1.12 for reference reactor with /bar T//sub e/ approx. = 21 keV. For the reference reactor P/sub f/ = 2880 MW so Q = 24. Without the bootstrap effect the absorbed current drive power would be P/sub CD/ = 285 MW, so T /equivalent to/ 1 - (/sub gamma///sub gamma//sup B)/ = 0.59. 10 refs., 9 figs., 2 tabs.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A series of tokamak equilibria are studied in order to identify characteristics which may maximize the proportion of toroidal current naturally provided by the bootstrap effect. These plasmas are typical of high field reactors considered by the ARIES (Advanced Reactor Innovation and Evaluation Study) collaboration and are assumed to have rather flat density profiles and broad pressure profiles. With the use of noninductive current drive to provide the seed current it is possible to operate with q/sub axis/ approx. = 2.0; this results in a (bootstrap-assissted) current drive power of P/sup B//sub CD/ - 117 MW and a figure of merit /sub gamma//sup B/ = 1.12 for reference reactor with /bar T//sub e/ approx. = 21 keV. For the reference reactor P/sub f/ = 2880 MW so Q = 24. Without the bootstrap effect the absorbed current drive power would be P/sub CD/ = 285 MW, so T /equivalent to/ 1 - (/sub gamma///sub gamma//sup B)/ = 0.59. 10 refs., 9 figs., 2 tabs.
Frontiers in Fusion Research II
Author: Mitsuru Kikuchi
Publisher: Springer
ISBN: 3319189050
Category : Technology & Engineering
Languages : en
Pages : 412
Book Description
This book reviews recent progress in our understanding of tokamak physics related to steady state operation, and addresses the scientific feasibility of a steady state tokamak fusion power system. It covers the physical principles behind continuous tokamak operation and details the challenges remaining and new lines of research towards the realization of such a system. Following a short introduction to tokamak physics and the fundamentals of steady state operation, later chapters cover parallel and perpendicular transport in tokamaks, MHD instabilities in advanced tokamak regimes, control issues, and SOL and divertor plasmas. A final chapter reviews key enabling technologies for steady state reactors, including negative ion source and NBI systems, Gyrotron and ECRF systems, superconductor and magnet systems, and structural materials for reactors. The tokamak has demonstrated an excellent plasma confinement capability with its symmetry, but has an intrinsic drawback with its pulsed operation with inductive operation. Efforts have been made over the last 20 years to realize steady state operation, most promisingly utilizing bootstrap current. Frontiers in Fusion Research II: Introduction to Modern Tokamak Physics will be of interest to graduate students and researchers involved in all aspects of tokamak science and technology.
Publisher: Springer
ISBN: 3319189050
Category : Technology & Engineering
Languages : en
Pages : 412
Book Description
This book reviews recent progress in our understanding of tokamak physics related to steady state operation, and addresses the scientific feasibility of a steady state tokamak fusion power system. It covers the physical principles behind continuous tokamak operation and details the challenges remaining and new lines of research towards the realization of such a system. Following a short introduction to tokamak physics and the fundamentals of steady state operation, later chapters cover parallel and perpendicular transport in tokamaks, MHD instabilities in advanced tokamak regimes, control issues, and SOL and divertor plasmas. A final chapter reviews key enabling technologies for steady state reactors, including negative ion source and NBI systems, Gyrotron and ECRF systems, superconductor and magnet systems, and structural materials for reactors. The tokamak has demonstrated an excellent plasma confinement capability with its symmetry, but has an intrinsic drawback with its pulsed operation with inductive operation. Efforts have been made over the last 20 years to realize steady state operation, most promisingly utilizing bootstrap current. Frontiers in Fusion Research II: Introduction to Modern Tokamak Physics will be of interest to graduate students and researchers involved in all aspects of tokamak science and technology.
Government Reports Announcements & Index
Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 1164
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 1164
Book Description
Fusion Technology 1990
Author: B.E. Keen
Publisher: Elsevier
ISBN: 0444600655
Category : Technology & Engineering
Languages : en
Pages : 1039
Book Description
The aim of the biennial series of symposia on Fusion Technology, organized by the European Fusion Laboratories, is the exchange of information on the design, construction and operation of fusion experiments. The coverage of the volume includes the technology aspects of fusion reactors to provide a link to the technology of new developments and form a guideline for the definition of future work. These proceedings comprise two volumes and contain both the invited lectures and contributed papers presented at the Symposium, which was attended by 556 participants from around the globe. The 312 papers in this volume, including 17 invited papers, give a broad and current overview of the progress and trends fusion technology is experiencing now, and the future for fusion devices.
Publisher: Elsevier
ISBN: 0444600655
Category : Technology & Engineering
Languages : en
Pages : 1039
Book Description
The aim of the biennial series of symposia on Fusion Technology, organized by the European Fusion Laboratories, is the exchange of information on the design, construction and operation of fusion experiments. The coverage of the volume includes the technology aspects of fusion reactors to provide a link to the technology of new developments and form a guideline for the definition of future work. These proceedings comprise two volumes and contain both the invited lectures and contributed papers presented at the Symposium, which was attended by 556 participants from around the globe. The 312 papers in this volume, including 17 invited papers, give a broad and current overview of the progress and trends fusion technology is experiencing now, and the future for fusion devices.