Direct extrapolation of radial profile data to a self-ignited fusion reactor based on the gyro-Bohm model-Reference-Cited by-同舟云学术

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Direct extrapolation of radial profile data to a self-ignited fusion reactor based on the gyro-Bohm model

Published:2011-12 Issue:12 Volume:86 Page:2879-2885
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Miyazawa J.,Goto T.,Morisaki T.,Goto M.,Sakamoto R.,Motojima G.,Peterson B.J.,Suzuki C.,Ida K.,Yamada H.,Sagara A.

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference33 articles.

1. Optimization activities on design studies of LHD-type reactor FFHR;Sagara;Fusion Eng. Des.,2008

2. Minimization of the external heating power by long fusion power rise-up time for self-ignition access in the helical reactor FFHR2m;Mitarai;Nucl. Fusion,2007

3. The Helias reactor HSR4/18;Beidler;Nucl. Fusion,2001

4. ARIES-CS team, The ARIES-CS compact stellarator fusion power plant;Najmabadi;Fusion Sci. Technol.,2008

5. Compact DEMO, SlimCS: design progress and issues;Tobita;Nucl. Fusion,2009

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1. Development of steady-state fusion reactor by Helical Fusion;Physics of Plasmas;2023-05-01

2. Feasibility study of tokamak, helical and laser reactors as affordable fusion volumetric neutron sources;Nuclear Fusion;2021-11-15

3. Novel features of the helical volumetric neutron source FFHR-b2;Nuclear Fusion;2021-10-04

4. Maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets;Fusion Engineering and Design;2018-11

5. Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1;Journal of Fusion Energy;2018-10-04

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