TY - JOUR
T1 - Characteristics of plasma operation with the ferritic inside wall and its compatibility with high-performance plasmas in JFT-2M
AU - Tsuzuki, K.
AU - Kimura, H.
AU - Kusama, Y.
AU - Sato, M.
AU - Kawashima, H.
AU - Kamiya, K.
AU - Shinohara, K.
AU - Ogawa, H.
AU - Uehara, K.
AU - Kurita, G.
AU - Kasai, S.
AU - Hoshino, K.
AU - Isei, N.
AU - Miura, Y.
AU - Yamamoto, M.
AU - Kikuchi, K.
AU - Shibata, T.
AU - Bakhtiari, M.
AU - Hino, T.
AU - Hirohata, Y.
AU - Yamauchi, Y.
AU - Yamaguchi, K.
AU - Tsutsui, H.
AU - Shimada, R.
AU - Amemiya, H.
AU - Nagashima, Y.
AU - Ido, T.
AU - Hamada, Y.
N1 - Copyright:
Copyright 2018 Elsevier B.V., All rights reserved.
PY - 2006/2
Y1 - 2006/2
N2 - Compatibility between plasma and reduced activation ferritic steel, which is the leading candidate for the structural material of a fusion demonstration reactor, has been investigated in the Advanced Material Tokamak EXperiment (AMTEX). Ferritic plates (FPs) were installed progressively in the JFT-2M tokamak. The effect of ferromagnetism on plasma production, control, confinement, and stability has been investigated. Impurity release behavior has also been investigated. Even when the inside vacuum vessel wall was fully covered with the FPs and the tokamak plasma was operated close to the wall, no deleterious effect was observed, and the normalized beta could be increased up to ∼3.5. Thus, encouraging results are obtained for application of this material to the demonstration reactor.
AB - Compatibility between plasma and reduced activation ferritic steel, which is the leading candidate for the structural material of a fusion demonstration reactor, has been investigated in the Advanced Material Tokamak EXperiment (AMTEX). Ferritic plates (FPs) were installed progressively in the JFT-2M tokamak. The effect of ferromagnetism on plasma production, control, confinement, and stability has been investigated. Impurity release behavior has also been investigated. Even when the inside vacuum vessel wall was fully covered with the FPs and the tokamak plasma was operated close to the wall, no deleterious effect was observed, and the normalized beta could be increased up to ∼3.5. Thus, encouraging results are obtained for application of this material to the demonstration reactor.
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U2 - 10.13182/FST06-A1095
DO - 10.13182/FST06-A1095
M3 - Article
AN - SCOPUS:33644609451
SN - 1536-1055
VL - 49
SP - 197
EP - 208
JO - Fusion Science and Technology
JF - Fusion Science and Technology
IS - 2
ER -