Iter Physics Design Guidelines At High Aspect Ratio
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Iter Physics Design Guidelines At High Aspect Ratio
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Author :
language : en
Publisher:
Release Date : 1991
Iter Physics Design Guidelines At High Aspect Ratio written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1991 with categories.
The physics requirements for ITER design are formulated in a set of physics design guidelines. These guidelines, established by the ITER Physics Group during the Conceptual Design Activity (CDA, 1988--90), were based on credible extrapolations of the tokamak physics database as assessed during the CDA, and defined a class of tokamak designs (with plasma current I (approximately)20 MA and aspect ratio A (approximately)2.5--3.5) that meet the ITER objectives. Recent US studies have indicated that there may be significant benefits if the ITER-CDA design point is moved from the low aspect ratio, high current baseline (A = 2.79, I = 22 MA) to a high aspect ratio machine at A (approximately)4, I (approximately)15 MA, especially regarding steady-state, technology-testing performance. To adequately assess the physics and technology testing capability of higher aspect ratio design options, several changes are proposed to the original ITER guidelines to reflect the latest (although limited) developments in physics understanding at higher aspect ratios. The critical issues for higher aspect ratio design options are the uncertainty in scaling of confinement with aspect ratio, the variation of vertical stability with elongation and aspect ratio, plasma shaping requirements, ability to control and maintain plasma current and q-profiles for MHD stability (and volt-second consumption), access for current drive, restrictions on field ripple and divertor plate incident angles, etc. 5 refs., 1 tab.
Scientific And Technical Aerospace Reports
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Author :
language : en
Publisher:
Release Date : 1995
Scientific And Technical Aerospace Reports written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1995 with Aeronautics categories.
Iter Parametric Analysis And Operational Performance
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Author :
language : en
Publisher:
Release Date : 1991
Iter Parametric Analysis And Operational Performance written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1991 with Engineering test reactors categories.
Government Reports Annual Index
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Author :
language : en
Publisher:
Release Date : 1994
Government Reports Annual Index written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1994 with Government reports announcements & index categories.
Energy Research Abstracts
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Author :
language : en
Publisher:
Release Date : 1994-03
Energy Research Abstracts written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1994-03 with Power resources categories.
Fusion Technology
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Author :
language : en
Publisher:
Release Date : 1994
Fusion Technology written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1994 with Fusion reactors categories.
Government Reports Announcements Index
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Author :
language : en
Publisher:
Release Date : 1993-05
Government Reports Announcements Index written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1993-05 with Science categories.
Fusion Technology 1992
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Author : C. Ferro
language : en
Publisher: Elsevier
Release Date : 2013-10-22
Fusion Technology 1992 written by C. Ferro and has been published by Elsevier this book supported file pdf, txt, epub, kindle and other format this book has been release on 2013-10-22 with Technology & Engineering categories.
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 and on the technology being developed for the next-step devices and fusion reactors. The coverage of the volume includes the technological aspects of fusion reactors in relation to new developments, thus forming a guideline for the definition of future work. These proceedings comprise three volumes and contain both the invited lectures and contributed papers presented at the symposium, which was attended by 569 participants from around the globe. The 343 papers, including 12 invited papers, characterise the increasing interest of industry in the fusion programme, giving a broad and current overview on the progress and trends fusion technology is experiencing now, as well as indicating the future for fusion devices.
Projections For A Steady State Tokamak Reactor Based On Iter
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Author :
language : en
Publisher:
Release Date : 1989
Projections For A Steady State Tokamak Reactor Based On Iter written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1989 with categories.
The extensions of the physics and engineering guidelines for the ITER device needed for acceptable operating points for a steady-state tokamak power reactor are examined. Non-inductive current drive is provided in steady state by high-energy neutral-beam injection in the plasma core, lower-hybrid slow waves in the outer regions of the plasma and (30%) bootstrap current. Three different levels of extension of the ITER physics/engineering guide-lines, with differing assumptions on the possible plasma beta, elongation and aspect ratio, are considered for power-reactor applications. Plasma gain, Q/sub p/ = fusion power/input power, in excess of 20 and average neutron wall fluxes from 2.3 to 3.6 MW/m2 are predicted in devices with major radii varying from 7.0 to 6.0 m and aspect ratios from 2.9 to 4. 3. Peak divertor heat fluxes range up to 12.2 MW/m2 which is somewhat higher than the current ITER design limit of 10 MW/m2 with a magnetically swept divertor. These designs were selected on the basis of improvements in physics/engineering consistent with time scales for development of future reactors. The design re-optimization on the basis of cost-of-electricity (COE) was then examined using a reactor systems model. This analysis generally verified the original estimates for the required extensions of the ITER guidelines. Cost of electricity is projected to be less than 66 mills/kW/sub e/h in all of the configurations. The smallest reactor, which has the largest neutron wall flux and mass power density, yields the lowest COE, 56 mills/kW/sub e/h. 37 refs., 8 figs., 11 tabs.
Mechanical Design Issues Associated With Mounting Maintenance And Handling Of An Iter Divertor
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Author :
language : en
Publisher:
Release Date : 1991
Mechanical Design Issues Associated With Mounting Maintenance And Handling Of An Iter Divertor written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1991 with categories.
Several designs that address plasma-facing plate configurations and thermal-hydraulic design issues have been developed for the ITER divertor. Design criteria growing out of physics requirements, physical constraints, and remote handling requirements impose severe mechanical requirements on the support structure and its attachments. These pose a challenge to the mechanical design of a divertor, which must be addressed before a functional divertor is practical -- that is, one that can be remotely handled, aligned, and maintained; that functions reliably under thermal loading and disruptions; and that gives the required life in the nuclear environment predicted for ITER. This paper discusses the design criteria for the divertor mounting structure and identifies the mechanical design issues that need to be addressed. Achieving the criteria may require the development of new components and innovative configurations, specifically a new class of remote fasteners and electrically resistant material for mounts. The possible design of such components and an R D program to develop them are described, and issues specific to the high-aspect-ratio design (HARD) configuration are summarized. Analysis and experiments that will resolve these issues and concerns and lead to a final ITER design are identified. 2 refs., 2 figs.