Journal ArticleDOI
Compact reversed shear tokamak reactor with a superheated steam cycle
Kunihiko Okano,Y. Asaoka,Tomoaki Yoshida,Masahiro Furuya,K. Tomabechi,Yuichi Ogawa,Naoto Sekimura,Ryoji Hiwatari,T. Yamamoto,T. Yamamoto,T. Ishikawa,Yuzo Fukai,Akiyoshi Hatayama,Nobuyuki Inoue,Akira Kohyama,K. Shinya,Y. Murakami,I. Senda,Seiichiro Yamazaki,Seiji Mori,J. Adachi,M. Takemoto +21 more
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TLDR
The compact reversed shear tokamak CREST (CREST) as discussed by the authors is a cost competitive nuclear power plant based on a reversed high β plasma and water cooled ferritic steel components.Abstract:
The compact reversed shear tokamak CREST is a cost competitive reactor concept based on a reversed shear high β plasma and water cooled ferritic steel components. The moderate aspect ratio A = 3.4 and the elongation κ = 2.0 of CREST are very similar to the case of the ITER advanced mode plasma. Presentation of such a concept based on the ITER project should be worth while for formulating a fusion development strategy. The achievement of a competitive cost of electricity (COE) is the first priority for electric power industries. High β and high thermal efficiency are the most effective parameters for achieving a competitive COE. In order to achieve a high efficiency power plant, a superheated steam cycle has been adopted which permits a high thermal efficiency (η = 41%). Current profile control and high speed plasma rotation by neutral beam current drive stabilize the ideal MHD activity up to the Troyon coefficient βN = 5.5. A cost assessment has shown that CREST could generate about 1.16 GW(e) electric power at a competitive cost.read more
Citations
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Journal ArticleDOI
Super-X divertors and high power density fusion devices
TL;DR: The Super-X Divertor (SXD) as mentioned in this paper is a robust axisymmetric redesign of the divertor magnetic geometry that can allow a fivefold increase in the core power density of toroidal fusion devices.
Journal ArticleDOI
On heat loading, novel divertors, and fusion reactors
TL;DR: In this article, a new class of X-divertors, called X-D, which considerably enhance the divertor thermal capacity through a flaring of the field lines only near the diversion plates, may be necessary and sufficient to overcome these problems.
Journal ArticleDOI
Design and technology development of solid breeder blanket cooled by supercritical water in Japan
Mikio Enoeda,Y. Kosaku,Toshihisa Hatano,T. Kuroda,N. Miki,T. Honma,Masato Akiba,Satoshi Konishi,Haruto Nakamura,Yoshinori Kawamura,Satoshi Sato,K. Furuya,Y. Asaoka,Kunihiko Okano +13 more
TL;DR: In this article, a hot isostatic pressing bonded F82H first wall mock-up with embedded rectangular cooling channels was successfully fabricated, which withstood the high heat flux test at 2.7 MW m−2.
Journal ArticleDOI
Fusion-Fission Transmutation Scheme—Efficient destruction of nuclear waste
TL;DR: In this paper, a fusion-assisted transmutation system for the destruction of transuranic nuclear waste is developed by combining a subcritical fusion-fission hybrid assembly uniquely equipped to burn the worst thermal nonfissile transuran isotopes with a new fuel cycle that uses cheaper light water reactors for most of the transmutation.
Journal ArticleDOI
SlimCS—compact low aspect ratio DEMO reactor with reduced-size central solenoid
Kenji Tobita,S. Nishio,M. Sato,Shinji Sakurai,Takumi Hayashi,Yusuke Shibama,Takaaki Isono,Mikio Enoeda,Hideo Nakamura,Satoshi Sato,Koichiro Ezato,Takanori Hirose,Shunsuke Ide,Takashi Inoue,Yutaka Kamada,Yoshinori Kawamura,Hisato Kawashima,Norikiyo Koizumi,G. Kurita,Y. Nakamura,K. Mouri,Takeo Nishitani,J. Ohmori,Naoyuki Oyama,Keishi Sakamoto,Satoshi Suzuki,T. Suzuki,Hiroyasu Tanigawa,Katsuhiko Tsuchiya,Daigo Tsuru +29 more
TL;DR: In this article, the concept of a compact DEMO reactor named "SlimCS" is presented, which uses a reduced-size center solenoid (CS) which has the function of plasma shaping rather than poloidal flux supply.
References
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Journal Article
Plasma Physics and Controlled Nuclear Fusion Research
TL;DR: In this paper, the first experiments in JET have been described, which show that this large tokamak behaves in a similar manner to smaller tokak, but with correspondingly improved plasma parameters.
Journal ArticleDOI
Erato stability code
Ralf Gruber,F. Troyon,D. Berger,L.C. Bernard,S. Rousset,R. Schreiber,Wolfgang Kerner,Wolf-Dieter Schneider,K.V. Roberts +8 more
TL;DR: This poster presents a probabilistic procedure for determining the carrier and removal of canine coronavirus from the blood stream through a simple, straightforward, and efficient procedure called “catch-and-catch” surgery.
Journal ArticleDOI
Overview of ARIES-RS tokamak fusion power plant
TL;DR: The ARIES-RS as discussed by the authors design study was initiated to examine a power plant based on the reversed-shear mode of plasma operation, coupled with a fusion power core which uses high-performance lithium-cooled vanadium components.
Journal ArticleDOI
Study of a compact reversed shear Tokamak reactor
Kunihiko Okano,Y. Asaoka,Ryoji Hiwatari,Nobuyuki Inoue,Y. Murakami,Yuichi Ogawa,K. Tokimatsu,K. Tomabechi,T. Yamamoto,Tomoaki Yoshida +9 more
TL;DR: In this article, the Compact Reversed Shear Tokamak, CREST-1, is designed with a moderate aspect ratio (R/a = 3.4), which will allow us to experimentally develop this CREST concept by ITER.
Journal ArticleDOI
Requirements of tritium breeding ratio for early fusion power reactors
TL;DR: In this paper, the requirements of tritium breeding ratio and the initial inventory for early fusion power reactors were investigated with a calculation model, and the results of calculated time-dependence of the time dependence of the breeding ratio were obtained.
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