Compact DEMO, SlimCS: Design progress and issues

K. Tobita; S. Nishio; M. Enoeda; H. Kawashima; G. Kurita; H. Tanigawa; H. Nakamura; M. Honda; A. Saito; S. Sato; T. Hayashi; N. Asakura; S. Sakurai; T. Nishitani; T. Ozeki; M. Ando; K. Ezato; K. Hamamatsu; T. Hirose; T. Hoshino; S. Ide; T. Inoue; T. Isono; C. Liu; S. Kakudate; Y. Kawamura; S. Mori; M. Nakamichi; H. Nishi; T. Nozawa; K. Ochiai; H. Ogiwara; N. Oyama; K. Sakamoto; Y. Sakamoto; Y. Seki; Y. Shibama; K. Shimizu; S. Suzuki; K. Takahashi; H. Tanigawa; D. Tsuru; T. Yamanishi; T. Yoshida

doi:10.1088/0029-5515/49/7/075029

Compact DEMO, SlimCS: Design progress and issues

K. Tobita, S. Nishio, M. Enoeda, H. Kawashima, G. Kurita, H. Tanigawa, H. Nakamura, M. Honda, A. Saito, S. Sato, T. Hayashi, N. Asakura, S. Sakurai, T. Nishitani, T. Ozeki, M. Ando, K. Ezato, K. Hamamatsu, T. Hirose, T. HoshinoS. Ide, T. Inoue, T. Isono, C. Liu, S. Kakudate, Y. Kawamura, S. Mori, M. Nakamichi, H. Nishi, T. Nozawa, K. Ochiai, H. Ogiwara, N. Oyama, K. Sakamoto, Y. Sakamoto, Y. Seki, Y. Shibama, K. Shimizu, S. Suzuki, K. Takahashi, H. Tanigawa, D. Tsuru, T. Yamanishi, T. Yoshida

ENG - Quantum Science and Energy Engineering

Japan Atomic Energy Agency

Research output: Contribution to journal › Article › peer-review

155 Citations (Scopus)

Abstract

The design progress in a compact low aspect ratio (low A) DEMO reactor, 'SlimCS', and its design issues are reported. The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme. For continuity with the Japanese ITER-TBM, the blanket is based on a water-cooled solid breeder blanket. For vertical stability of the elongated plasma and high beta access, the blanket is segmented into replaceable and permanent blankets and a sector-wide conducting shell is arranged inbetween these blankets. A numerical calculation indicates that fuel self-sufficiency can be satisfied when the blanket interior is ideally fabricated. An allowable heat load to the divertor plate should be 8 MW m^-2 or lower, which can be a critical constraint for determining a handling power of DEMO.

Original language	English
Article number	075029
Journal	Nuclear Fusion
Volume	49
Issue number	7
DOIs	https://doi.org/10.1088/0029-5515/49/7/075029
Publication status	Published - 2009

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Tobita, K., Nishio, S., Enoeda, M., Kawashima, H., Kurita, G., Tanigawa, H., Nakamura, H., Honda, M., Saito, A., Sato, S., Hayashi, T., Asakura, N., Sakurai, S., Nishitani, T., Ozeki, T., Ando, M., Ezato, K., Hamamatsu, K., Hirose, T., ... Yoshida, T. (2009). Compact DEMO, SlimCS: Design progress and issues. Nuclear Fusion, 49(7), Article 075029. https://doi.org/10.1088/0029-5515/49/7/075029

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title = "Compact DEMO, SlimCS: Design progress and issues",

abstract = "The design progress in a compact low aspect ratio (low A) DEMO reactor, 'SlimCS', and its design issues are reported. The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme. For continuity with the Japanese ITER-TBM, the blanket is based on a water-cooled solid breeder blanket. For vertical stability of the elongated plasma and high beta access, the blanket is segmented into replaceable and permanent blankets and a sector-wide conducting shell is arranged inbetween these blankets. A numerical calculation indicates that fuel self-sufficiency can be satisfied when the blanket interior is ideally fabricated. An allowable heat load to the divertor plate should be 8 MW m-2 or lower, which can be a critical constraint for determining a handling power of DEMO.",

author = "K. Tobita and S. Nishio and M. Enoeda and H. Kawashima and G. Kurita and H. Tanigawa and H. Nakamura and M. Honda and A. Saito and S. Sato and T. Hayashi and N. Asakura and S. Sakurai and T. Nishitani and T. Ozeki and M. Ando and K. Ezato and K. Hamamatsu and T. Hirose and T. Hoshino and S. Ide and T. Inoue and T. Isono and C. Liu and S. Kakudate and Y. Kawamura and S. Mori and M. Nakamichi and H. Nishi and T. Nozawa and K. Ochiai and H. Ogiwara and N. Oyama and K. Sakamoto and Y. Sakamoto and Y. Seki and Y. Shibama and K. Shimizu and S. Suzuki and K. Takahashi and H. Tanigawa and D. Tsuru and T. Yamanishi and T. Yoshida",

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doi = "10.1088/0029-5515/49/7/075029",

language = "English",

volume = "49",

journal = "Nuclear Fusion",

issn = "0029-5515",

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Tobita, K, Nishio, S, Enoeda, M, Kawashima, H, Kurita, G, Tanigawa, H, Nakamura, H, Honda, M, Saito, A, Sato, S, Hayashi, T, Asakura, N, Sakurai, S, Nishitani, T, Ozeki, T, Ando, M, Ezato, K, Hamamatsu, K, Hirose, T, Hoshino, T, Ide, S, Inoue, T, Isono, T, Liu, C, Kakudate, S, Kawamura, Y, Mori, S, Nakamichi, M, Nishi, H, Nozawa, T, Ochiai, K, Ogiwara, H, Oyama, N, Sakamoto, K, Sakamoto, Y, Seki, Y, Shibama, Y, Shimizu, K, Suzuki, S, Takahashi, K, Tanigawa, H, Tsuru, D, Yamanishi, T & Yoshida, T 2009, 'Compact DEMO, SlimCS: Design progress and issues', Nuclear Fusion, vol. 49, no. 7, 075029. https://doi.org/10.1088/0029-5515/49/7/075029

TY - JOUR

T1 - Compact DEMO, SlimCS

T2 - Design progress and issues

AU - Tobita, K.

AU - Nishio, S.

AU - Enoeda, M.

AU - Kawashima, H.

AU - Kurita, G.

AU - Tanigawa, H.

AU - Nakamura, H.

AU - Honda, M.

AU - Saito, A.

AU - Sato, S.

AU - Hayashi, T.

AU - Asakura, N.

AU - Sakurai, S.

AU - Nishitani, T.

AU - Ozeki, T.

AU - Ando, M.

AU - Ezato, K.

AU - Hamamatsu, K.

AU - Hirose, T.

AU - Hoshino, T.

AU - Ide, S.

AU - Inoue, T.

AU - Isono, T.

AU - Liu, C.

AU - Kakudate, S.

AU - Kawamura, Y.

AU - Mori, S.

AU - Nakamichi, M.

AU - Nishi, H.

AU - Nozawa, T.

AU - Ochiai, K.

AU - Ogiwara, H.

AU - Oyama, N.

AU - Sakamoto, K.

AU - Sakamoto, Y.

AU - Seki, Y.

AU - Shibama, Y.

AU - Shimizu, K.

AU - Suzuki, S.

AU - Takahashi, K.

AU - Tanigawa, H.

AU - Tsuru, D.

AU - Yamanishi, T.

AU - Yoshida, T.

PY - 2009

Y1 - 2009

N2 - The design progress in a compact low aspect ratio (low A) DEMO reactor, 'SlimCS', and its design issues are reported. The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme. For continuity with the Japanese ITER-TBM, the blanket is based on a water-cooled solid breeder blanket. For vertical stability of the elongated plasma and high beta access, the blanket is segmented into replaceable and permanent blankets and a sector-wide conducting shell is arranged inbetween these blankets. A numerical calculation indicates that fuel self-sufficiency can be satisfied when the blanket interior is ideally fabricated. An allowable heat load to the divertor plate should be 8 MW m-2 or lower, which can be a critical constraint for determining a handling power of DEMO.

AB - The design progress in a compact low aspect ratio (low A) DEMO reactor, 'SlimCS', and its design issues are reported. The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme. For continuity with the Japanese ITER-TBM, the blanket is based on a water-cooled solid breeder blanket. For vertical stability of the elongated plasma and high beta access, the blanket is segmented into replaceable and permanent blankets and a sector-wide conducting shell is arranged inbetween these blankets. A numerical calculation indicates that fuel self-sufficiency can be satisfied when the blanket interior is ideally fabricated. An allowable heat load to the divertor plate should be 8 MW m-2 or lower, which can be a critical constraint for determining a handling power of DEMO.

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U2 - 10.1088/0029-5515/49/7/075029

DO - 10.1088/0029-5515/49/7/075029

M3 - Article

AN - SCOPUS:70349091036

SN - 0029-5515

VL - 49

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 7

M1 - 075029

ER -

Compact DEMO, SlimCS: Design progress and issues

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