High performance tokamak experiments with a ferritic steel wall on JFT-2M

K. Tsuzuki; H. Kimura; H. Kawashima; M. Sato; K. Kamiya; K. Shinohara; H. Ogawa; K. Hoshino; M. Bakhtiari; S. Kasai; K. Uehara; H. Sasao; Y. Kusama; N. Isei; Y. Miura; T. Ogawa; M. Yamamoto; T. Shibata; K. Kikuchi; K. Miyachi; T. Ito; H. Ajikawa; S. Nomura; H. Tsutsui; R. Shimada; T. Ido; Y. Hamada; N. Fukumoto; M. Nagata; T. Uyama; H. Niimi; S. Yatsu; N. Kayukawa; T. Hino; Y. Hirohata; Y. Nagashima; A. Ejiri; A. Amemiya; Y. Sadamoto; A. Tsushima

doi:10.1088/0029-5515/43/10/033

High performance tokamak experiments with a ferritic steel wall on JFT-2M

K. Tsuzuki, H. Kimura, H. Kawashima, M. Sato, K. Kamiya, K. Shinohara, H. Ogawa, K. Hoshino, M. Bakhtiari, S. Kasai, K. Uehara, H. Sasao, Y. Kusama, N. Isei, Y. Miura, T. Ogawa, M. Yamamoto, T. Shibata, K. Kikuchi, K. MiyachiT. Ito, H. Ajikawa, S. Nomura, H. Tsutsui, R. Shimada, T. Ido, Y. Hamada, N. Fukumoto, M. Nagata, T. Uyama, H. Niimi, S. Yatsu, N. Kayukawa, T. Hino, Y. Hirohata, Y. Nagashima, A. Ejiri, A. Amemiya, Y. Sadamoto, A. Tsushima

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42 Citations (Scopus)

Abstract

Compatibility between the plasma and low activation ferritic steel, which is a candidate material for fusion demonstration reactors, has been investigated step by step in the JFT-2M tokamak. We have entered the third stage of the Advanced Material Tokamak EXperiment (AMTEX), where the inside of the vacuum vessel wall is completely covered with ferritic steel plates ferritic inside wall (FIW). The effects of a FIW on the plasma production, impurity release, the operation region, and H-mode characteristics have been investigated. No negative effect has been observed up to now. A high normalized beta plasma of β_N ∼ 3, having both an internal transport barrier and a steady H-mode edge was obtained. A remarkable reduction in ripple trapped loss from 0.26 MW m^-2 (without ferritic steel) to less than 0.01 MW m^-2 was demonstrated by the optimization of the thickness profile of FIW. A code to calculate fast ion losses, taking into account the full three-dimensional magnetic structure was developed, and values obtained using the code showed good agreement with experimental results. Thus, encouraging results are obtained for the use of this material in the demo-reactor.

Original language	English
Pages (from-to)	1288-1293
Number of pages	6
Journal	Nuclear Fusion
Volume	43
Issue number	10
DOIs	https://doi.org/10.1088/0029-5515/43/10/033
Publication status	Published - Oct 2003
Externally published	Yes

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Condensed Matter Physics

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10.1088/0029-5515/43/10/033

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Tsuzuki, K., Kimura, H., Kawashima, H., Sato, M., Kamiya, K., Shinohara, K., Ogawa, H., Hoshino, K., Bakhtiari, M., Kasai, S., Uehara, K., Sasao, H., Kusama, Y., Isei, N., Miura, Y., Ogawa, T., Yamamoto, M., Shibata, T., Kikuchi, K., ... Tsushima, A. (2003). High performance tokamak experiments with a ferritic steel wall on JFT-2M. Nuclear Fusion, 43(10), 1288-1293. https://doi.org/10.1088/0029-5515/43/10/033

Tsuzuki, K, Kimura, H, Kawashima, H, Sato, M, Kamiya, K, Shinohara, K, Ogawa, H, Hoshino, K, Bakhtiari, M, Kasai, S, Uehara, K, Sasao, H, Kusama, Y, Isei, N, Miura, Y, Ogawa, T, Yamamoto, M, Shibata, T, Kikuchi, K, Miyachi, K, Ito, T, Ajikawa, H, Nomura, S, Tsutsui, H, Shimada, R, Ido, T, Hamada, Y, Fukumoto, N, Nagata, M, Uyama, T, Niimi, H, Yatsu, S, Kayukawa, N, Hino, T, Hirohata, Y, Nagashima, Y, Ejiri, A, Amemiya, A, Sadamoto, Y & Tsushima, A 2003, 'High performance tokamak experiments with a ferritic steel wall on JFT-2M', Nuclear Fusion, vol. 43, no. 10, pp. 1288-1293. https://doi.org/10.1088/0029-5515/43/10/033

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title = "High performance tokamak experiments with a ferritic steel wall on JFT-2M",

abstract = "Compatibility between the plasma and low activation ferritic steel, which is a candidate material for fusion demonstration reactors, has been investigated step by step in the JFT-2M tokamak. We have entered the third stage of the Advanced Material Tokamak EXperiment (AMTEX), where the inside of the vacuum vessel wall is completely covered with ferritic steel plates ferritic inside wall (FIW). The effects of a FIW on the plasma production, impurity release, the operation region, and H-mode characteristics have been investigated. No negative effect has been observed up to now. A high normalized beta plasma of βN ∼ 3, having both an internal transport barrier and a steady H-mode edge was obtained. A remarkable reduction in ripple trapped loss from 0.26 MW m-2 (without ferritic steel) to less than 0.01 MW m-2 was demonstrated by the optimization of the thickness profile of FIW. A code to calculate fast ion losses, taking into account the full three-dimensional magnetic structure was developed, and values obtained using the code showed good agreement with experimental results. Thus, encouraging results are obtained for the use of this material in the demo-reactor.",

author = "K. Tsuzuki and H. Kimura and H. Kawashima and M. Sato and K. Kamiya and K. Shinohara and H. Ogawa and K. Hoshino and M. Bakhtiari and S. Kasai and K. Uehara and H. Sasao and Y. Kusama and N. Isei and Y. Miura and T. Ogawa and M. Yamamoto and T. Shibata and K. Kikuchi and K. Miyachi and T. Ito and H. Ajikawa and S. Nomura and H. Tsutsui and R. Shimada and T. Ido and Y. Hamada and N. Fukumoto and M. Nagata and T. Uyama and H. Niimi and S. Yatsu and N. Kayukawa and T. Hino and Y. Hirohata and Y. Nagashima and A. Ejiri and A. Amemiya and Y. Sadamoto and A. Tsushima",

year = "2003",

month = oct,

doi = "10.1088/0029-5515/43/10/033",

language = "English",

volume = "43",

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journal = "Nuclear Fusion",

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T1 - High performance tokamak experiments with a ferritic steel wall on JFT-2M

AU - Tsuzuki, K.

AU - Kimura, H.

AU - Kawashima, H.

AU - Sato, M.

AU - Kamiya, K.

AU - Shinohara, K.

AU - Ogawa, H.

AU - Hoshino, K.

AU - Bakhtiari, M.

AU - Kasai, S.

AU - Uehara, K.

AU - Sasao, H.

AU - Kusama, Y.

AU - Isei, N.

AU - Miura, Y.

AU - Ogawa, T.

AU - Yamamoto, M.

AU - Shibata, T.

AU - Kikuchi, K.

AU - Miyachi, K.

AU - Ito, T.

AU - Ajikawa, H.

AU - Nomura, S.

AU - Tsutsui, H.

AU - Shimada, R.

AU - Ido, T.

AU - Hamada, Y.

AU - Fukumoto, N.

AU - Nagata, M.

AU - Uyama, T.

AU - Niimi, H.

AU - Yatsu, S.

AU - Kayukawa, N.

AU - Hino, T.

AU - Hirohata, Y.

AU - Nagashima, Y.

AU - Ejiri, A.

AU - Amemiya, A.

AU - Sadamoto, Y.

AU - Tsushima, A.

PY - 2003/10

Y1 - 2003/10

N2 - Compatibility between the plasma and low activation ferritic steel, which is a candidate material for fusion demonstration reactors, has been investigated step by step in the JFT-2M tokamak. We have entered the third stage of the Advanced Material Tokamak EXperiment (AMTEX), where the inside of the vacuum vessel wall is completely covered with ferritic steel plates ferritic inside wall (FIW). The effects of a FIW on the plasma production, impurity release, the operation region, and H-mode characteristics have been investigated. No negative effect has been observed up to now. A high normalized beta plasma of βN ∼ 3, having both an internal transport barrier and a steady H-mode edge was obtained. A remarkable reduction in ripple trapped loss from 0.26 MW m-2 (without ferritic steel) to less than 0.01 MW m-2 was demonstrated by the optimization of the thickness profile of FIW. A code to calculate fast ion losses, taking into account the full three-dimensional magnetic structure was developed, and values obtained using the code showed good agreement with experimental results. Thus, encouraging results are obtained for the use of this material in the demo-reactor.

AB - Compatibility between the plasma and low activation ferritic steel, which is a candidate material for fusion demonstration reactors, has been investigated step by step in the JFT-2M tokamak. We have entered the third stage of the Advanced Material Tokamak EXperiment (AMTEX), where the inside of the vacuum vessel wall is completely covered with ferritic steel plates ferritic inside wall (FIW). The effects of a FIW on the plasma production, impurity release, the operation region, and H-mode characteristics have been investigated. No negative effect has been observed up to now. A high normalized beta plasma of βN ∼ 3, having both an internal transport barrier and a steady H-mode edge was obtained. A remarkable reduction in ripple trapped loss from 0.26 MW m-2 (without ferritic steel) to less than 0.01 MW m-2 was demonstrated by the optimization of the thickness profile of FIW. A code to calculate fast ion losses, taking into account the full three-dimensional magnetic structure was developed, and values obtained using the code showed good agreement with experimental results. Thus, encouraging results are obtained for the use of this material in the demo-reactor.

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DO - 10.1088/0029-5515/43/10/033

M3 - Article

AN - SCOPUS:0242380273

SN - 0029-5515

VL - 43

SP - 1288

EP - 1293

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 10

ER -

High performance tokamak experiments with a ferritic steel wall on JFT-2M

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