Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Computational Model for Superconducting Toroidal-Field Magnets for a Tokamak Reactor
Thermo-hydraulic Analysis of Superconducting Toroidal-field Magnets for the Tokamak Physics Experiment
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 10
Book Description
The superconducting magnets in Fusion Reactors are subjected to pulsed, nuclear, and resistive heating. The thermo-hydraulic response of the helium forced-flow cooled conductors to the various heat sources is critical to magnet design and performance. Recently developed computer codes allow accurate modeling of conductor response and have been used as an aid to design of the toroidal field (TF) magnets for the Tokamak Physics experiment (TPX). We present results of design studies that determine the trade-off between double- and single-pancake helium flow configurations, the minimum-temperature margin, and the stability against rapid heat input. The results guide the choice and design of the liquid helium refrigerator.
Publisher:
ISBN:
Category :
Languages : en
Pages : 10
Book Description
The superconducting magnets in Fusion Reactors are subjected to pulsed, nuclear, and resistive heating. The thermo-hydraulic response of the helium forced-flow cooled conductors to the various heat sources is critical to magnet design and performance. Recently developed computer codes allow accurate modeling of conductor response and have been used as an aid to design of the toroidal field (TF) magnets for the Tokamak Physics experiment (TPX). We present results of design studies that determine the trade-off between double- and single-pancake helium flow configurations, the minimum-temperature margin, and the stability against rapid heat input. The results guide the choice and design of the liquid helium refrigerator.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 636
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 636
Book Description
Fusion Energy Update
Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 160
Book Description
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 160
Book Description
Superconducting Devices & Materials
Author:
Publisher:
ISBN:
Category : Cryotrons
Languages : en
Pages : 656
Book Description
Publisher:
ISBN:
Category : Cryotrons
Languages : en
Pages : 656
Book Description
Conceptual Studies of Toroidal Field Magnets for the Tokamak Experimental Power Reactor. Final Report
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
This report documents the principal results of a Conceptual Design Study for the Superconducting Toroidal Field System for a Tokamak Experimental Power Reactor. Two concepts are described for peak operating fields at the windings of 8 tesla, and 12 tesla, respectively. The design and manufacturing considerations are treated in sufficient detail that cost and schedule estimates could be developed. Major uncertainties in the design are identified and their potential impact discussed, along with recommendations for the necessary research and development programs to minimize these uncertainties. The minimum dimensions of a sub-size test coil for experimental qualification of the full size design are developed and a test program is recommended.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
This report documents the principal results of a Conceptual Design Study for the Superconducting Toroidal Field System for a Tokamak Experimental Power Reactor. Two concepts are described for peak operating fields at the windings of 8 tesla, and 12 tesla, respectively. The design and manufacturing considerations are treated in sufficient detail that cost and schedule estimates could be developed. Major uncertainties in the design are identified and their potential impact discussed, along with recommendations for the necessary research and development programs to minimize these uncertainties. The minimum dimensions of a sub-size test coil for experimental qualification of the full size design are developed and a test program is recommended.
Fundamentals of Magnetic Thermonuclear Reactor Design
Author: Vasilij A. Glukhikh
Publisher: Woodhead Publishing
ISBN: 0081024711
Category : Technology & Engineering
Languages : en
Pages : 476
Book Description
Fundamentals of Magnetic Thermonuclear Reactor Design is a comprehensive resource on fusion technology and energy systems written by renowned scientists and engineers from the Russian nuclear industry. It brings together a wealth of invaluable experience and knowledge on controlled thermonuclear fusion (CTF) facilities with magnetic plasma confinement – from the first semi-commercial tokamak T-3, to the multi-billion international experimental thermonuclear reactor ITER, now in construction in France. As the INTOR and ITER projects have made an immense contribution in the past few decades, this book focuses on its practical engineering aspects and the basics of technical physics and electrical engineering. Users will gain an understanding of the key ratios between plasma and technical parameters, design streamlining algorithms and engineering solutions. - Written by a team of qualified experts who have been involved in the design of thermonuclear reactors for over 50 years - Outlines the most important features of the ITER project in France which is building the largest tokamak, including the design, material selection, safety and economic considerations - Includes data on how to design magnetic fusion reactors using CAD tools, along with relevant regulatory documents
Publisher: Woodhead Publishing
ISBN: 0081024711
Category : Technology & Engineering
Languages : en
Pages : 476
Book Description
Fundamentals of Magnetic Thermonuclear Reactor Design is a comprehensive resource on fusion technology and energy systems written by renowned scientists and engineers from the Russian nuclear industry. It brings together a wealth of invaluable experience and knowledge on controlled thermonuclear fusion (CTF) facilities with magnetic plasma confinement – from the first semi-commercial tokamak T-3, to the multi-billion international experimental thermonuclear reactor ITER, now in construction in France. As the INTOR and ITER projects have made an immense contribution in the past few decades, this book focuses on its practical engineering aspects and the basics of technical physics and electrical engineering. Users will gain an understanding of the key ratios between plasma and technical parameters, design streamlining algorithms and engineering solutions. - Written by a team of qualified experts who have been involved in the design of thermonuclear reactors for over 50 years - Outlines the most important features of the ITER project in France which is building the largest tokamak, including the design, material selection, safety and economic considerations - Includes data on how to design magnetic fusion reactors using CAD tools, along with relevant regulatory documents
Energy
Author:
Publisher:
ISBN:
Category : Fuel
Languages : en
Pages : 514
Book Description
Publisher:
ISBN:
Category : Fuel
Languages : en
Pages : 514
Book Description
Thermo-hydraulic Analysis of the TPX Superconducting TF Magnets
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6
Book Description
The superconducting magnets in Fusion Reactors are subjected to pulsed, nuclear, and resistive heating. The thermo-hydraulic response of the helium forced-flow cooled conductors to the various heat sources is critical to magnet design and performance. Recently developed computer codes allow accurate modeling of conductor response and have been used as an aid to design of the toroidal field (TF) magnets for the Tokamak Physics eXperiment (TPX). The authors present results of design studies that determine the trade-off between double- and single-pancake helium-flow configurations.
Publisher:
ISBN:
Category :
Languages : en
Pages : 6
Book Description
The superconducting magnets in Fusion Reactors are subjected to pulsed, nuclear, and resistive heating. The thermo-hydraulic response of the helium forced-flow cooled conductors to the various heat sources is critical to magnet design and performance. Recently developed computer codes allow accurate modeling of conductor response and have been used as an aid to design of the toroidal field (TF) magnets for the Tokamak Physics eXperiment (TPX). The authors present results of design studies that determine the trade-off between double- and single-pancake helium-flow configurations.
International Aerospace Abstracts
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1076
Book Description
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1076
Book Description