Design study of fusion DEMO plant at JAERI

K. Tobita; S. Nishio; M. Enoeda; M. Sato; T. Isono; S. Sakurai; H. Nakamura; S. Sato; S. Suzuki; M. Ando; K. Ezato; T. Hayashi; T. Hirose; T. Inoue; Y. Kawamura; N. Koizumi; Y. Kudo; R. Kurihara; T. Kuroda; M. Matsukawa; K. Mouri; Y. Nakamura; M. Nishi; Y. Nomoto; J. Ohmori; N. Oyama; K. Sakamoto; T. Suzuki; M. Takechi; H. Tanigawa; K. Tsuchiya; D. Tsuru

doi:10.1016/j.fusengdes.2005.08.058

Design study of fusion DEMO plant at JAERI

K. Tobita, S. Nishio, M. Enoeda, M. Sato, T. Isono, S. Sakurai, H. Nakamura, S. Sato, S. Suzuki, M. Ando, K. Ezato, T. Hayashi, T. Hirose, T. Inoue, Y. Kawamura, N. Koizumi, Y. Kudo, R. Kurihara, T. Kuroda, M. MatsukawaK. Mouri, Y. Nakamura, M. Nishi, Y. Nomoto, J. Ohmori, N. Oyama, K. Sakamoto, T. Suzuki, M. Takechi, H. Tanigawa, K. Tsuchiya, D. Tsuru

ENG - Quantum Science and Energy Engineering

Research output: Contribution to journal › Conference article › peer-review

141 Citations (Scopus)

Abstract

Three options of fusion DEMO plant are proposed characterized by functions of the center solenoid (CS). The prime option uses a downsized CS, which does not provide sufficient V-s for plasma current ramp-up but supplies enough coil current for plasma shaping. This option produces a fusion output of 3 GW with a major radius of 5.5 m, aspect ratio of 2.6, normalized beta of 4.3 and maximum field of 16.4 T. The estimated reactor weight is lighter than that of other conventional tokamak reactors, suggesting an economic advantage. The plant uses rather conservative technologies such as Nb₃Al superconductor, water-cooled solid breeder blanket, low activation ferritic steel as the structural material and tungsten monoblock divertor plate. The design philosophy and key issues related to the constituent technologies of the plant are described in the present paper.

Original language	English
Pages (from-to)	1151-1158
Number of pages	8
Journal	Fusion Engineering and Design
Volume	81
Issue number	8-14 PART B
DOIs	https://doi.org/10.1016/j.fusengdes.2005.08.058
Publication status	Published - 2006 Feb
Event	Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B - Duration: 2005 May 22 → 2005 May 27

Keywords

Center solenoid
Compact reactor
DEMO
Low aspect ratio
Reactor design

Access to Document

10.1016/j.fusengdes.2005.08.058

Cite this

Tobita, K., Nishio, S., Enoeda, M., Sato, M., Isono, T., Sakurai, S., Nakamura, H., Sato, S., Suzuki, S., Ando, M., Ezato, K., Hayashi, T., Hirose, T., Inoue, T., Kawamura, Y., Koizumi, N., Kudo, Y., Kurihara, R., Kuroda, T., ... Tsuru, D. (2006). Design study of fusion DEMO plant at JAERI. Fusion Engineering and Design, 81(8-14 PART B), 1151-1158. https://doi.org/10.1016/j.fusengdes.2005.08.058

@article{ad43b1eff5a3469db316449b9f5010f1,

title = "Design study of fusion DEMO plant at JAERI",

abstract = "Three options of fusion DEMO plant are proposed characterized by functions of the center solenoid (CS). The prime option uses a downsized CS, which does not provide sufficient V-s for plasma current ramp-up but supplies enough coil current for plasma shaping. This option produces a fusion output of 3 GW with a major radius of 5.5 m, aspect ratio of 2.6, normalized beta of 4.3 and maximum field of 16.4 T. The estimated reactor weight is lighter than that of other conventional tokamak reactors, suggesting an economic advantage. The plant uses rather conservative technologies such as Nb3Al superconductor, water-cooled solid breeder blanket, low activation ferritic steel as the structural material and tungsten monoblock divertor plate. The design philosophy and key issues related to the constituent technologies of the plant are described in the present paper.",

keywords = "Center solenoid, Compact reactor, DEMO, Low aspect ratio, Reactor design",

author = "K. Tobita and S. Nishio and M. Enoeda and M. Sato and T. Isono and S. Sakurai and H. Nakamura and S. Sato and S. Suzuki and M. Ando and K. Ezato and T. Hayashi and T. Hirose and T. Inoue and Y. Kawamura and N. Koizumi and Y. Kudo and R. Kurihara and T. Kuroda and M. Matsukawa and K. Mouri and Y. Nakamura and M. Nishi and Y. Nomoto and J. Ohmori and N. Oyama and K. Sakamoto and T. Suzuki and M. Takechi and H. Tanigawa and K. Tsuchiya and D. Tsuru",

year = "2006",

month = feb,

doi = "10.1016/j.fusengdes.2005.08.058",

language = "English",

volume = "81",

pages = "1151--1158",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier BV",

number = "8-14 PART B",

note = "Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B ; Conference date: 22-05-2005 Through 27-05-2005",

}

Tobita, K, Nishio, S, Enoeda, M, Sato, M, Isono, T, Sakurai, S, Nakamura, H, Sato, S, Suzuki, S, Ando, M, Ezato, K, Hayashi, T, Hirose, T, Inoue, T, Kawamura, Y, Koizumi, N, Kudo, Y, Kurihara, R, Kuroda, T, Matsukawa, M, Mouri, K, Nakamura, Y, Nishi, M, Nomoto, Y, Ohmori, J, Oyama, N, Sakamoto, K, Suzuki, T, Takechi, M, Tanigawa, H, Tsuchiya, K & Tsuru, D 2006, 'Design study of fusion DEMO plant at JAERI', Fusion Engineering and Design, vol. 81, no. 8-14 PART B, pp. 1151-1158. https://doi.org/10.1016/j.fusengdes.2005.08.058

TY - JOUR

T1 - Design study of fusion DEMO plant at JAERI

AU - Tobita, K.

AU - Nishio, S.

AU - Enoeda, M.

AU - Sato, M.

AU - Isono, T.

AU - Sakurai, S.

AU - Nakamura, H.

AU - Sato, S.

AU - Suzuki, S.

AU - Ando, M.

AU - Ezato, K.

AU - Hayashi, T.

AU - Hirose, T.

AU - Inoue, T.

AU - Kawamura, Y.

AU - Koizumi, N.

AU - Kudo, Y.

AU - Kurihara, R.

AU - Kuroda, T.

AU - Matsukawa, M.

AU - Mouri, K.

AU - Nakamura, Y.

AU - Nishi, M.

AU - Nomoto, Y.

AU - Ohmori, J.

AU - Oyama, N.

AU - Sakamoto, K.

AU - Suzuki, T.

AU - Takechi, M.

AU - Tanigawa, H.

AU - Tsuchiya, K.

AU - Tsuru, D.

PY - 2006/2

Y1 - 2006/2

N2 - Three options of fusion DEMO plant are proposed characterized by functions of the center solenoid (CS). The prime option uses a downsized CS, which does not provide sufficient V-s for plasma current ramp-up but supplies enough coil current for plasma shaping. This option produces a fusion output of 3 GW with a major radius of 5.5 m, aspect ratio of 2.6, normalized beta of 4.3 and maximum field of 16.4 T. The estimated reactor weight is lighter than that of other conventional tokamak reactors, suggesting an economic advantage. The plant uses rather conservative technologies such as Nb3Al superconductor, water-cooled solid breeder blanket, low activation ferritic steel as the structural material and tungsten monoblock divertor plate. The design philosophy and key issues related to the constituent technologies of the plant are described in the present paper.

AB - Three options of fusion DEMO plant are proposed characterized by functions of the center solenoid (CS). The prime option uses a downsized CS, which does not provide sufficient V-s for plasma current ramp-up but supplies enough coil current for plasma shaping. This option produces a fusion output of 3 GW with a major radius of 5.5 m, aspect ratio of 2.6, normalized beta of 4.3 and maximum field of 16.4 T. The estimated reactor weight is lighter than that of other conventional tokamak reactors, suggesting an economic advantage. The plant uses rather conservative technologies such as Nb3Al superconductor, water-cooled solid breeder blanket, low activation ferritic steel as the structural material and tungsten monoblock divertor plate. The design philosophy and key issues related to the constituent technologies of the plant are described in the present paper.

KW - Center solenoid

KW - Compact reactor

KW - DEMO

KW - Low aspect ratio

KW - Reactor design

UR - http://www.scopus.com/inward/record.url?scp=32444450868&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=32444450868&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2005.08.058

DO - 10.1016/j.fusengdes.2005.08.058

M3 - Conference article

AN - SCOPUS:32444450868

SN - 0920-3796

VL - 81

SP - 1151

EP - 1158

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 8-14 PART B

T2 - Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B

Y2 - 22 May 2005 through 27 May 2005

ER -

Design study of fusion DEMO plant at JAERI

Abstract

Keywords

Access to Document

Other files and links

Fingerprint

Cite this