TY - JOUR
T1 - Control of the radial electric field shear by modification of the magnetic field configuration in LHD
AU - Ida, K.
AU - Yoshinuma, M.
AU - Yokoyama, M.
AU - Inagaki, S.
AU - Tamura, N.
AU - Peterson, B. J.
AU - Morisaki, T.
AU - Masuzaki, S.
AU - Komori, A.
AU - Nagayama, Y.
AU - Tanaka, K.
AU - Narihara, K.
AU - Watanabe, K. Y.
AU - Beidler, C. D.
PY - 2005/5/1
Y1 - 2005/5/1
N2 - Control of the radial electric field, Er, is considered to be important in helical plasmas, because the radial electric field and its shear are expected to reduce neoclassical and anomalous transport, respectively. In general, the radial electric field can be controlled by changing the collisionality, and positive or negative electric fields have been obtained by decreasing or increasing the electron density, respectively. Although the sign of the radial electric field can be controlled by changing the collisionality, modification of the magnetic field is required to achieve further control of the radial electric field, especially to produce a strong radial electric field shear. In the Large Helical Device (LHD) the radial electric field profiles are shown to be controlled by the modification of the magnetic field by (1) changing the radial profile of the effective helical ripples, ε h, (2) creating a magnetic island with an external perturbation field coil and (3) changing the local island divertor coil current.
AB - Control of the radial electric field, Er, is considered to be important in helical plasmas, because the radial electric field and its shear are expected to reduce neoclassical and anomalous transport, respectively. In general, the radial electric field can be controlled by changing the collisionality, and positive or negative electric fields have been obtained by decreasing or increasing the electron density, respectively. Although the sign of the radial electric field can be controlled by changing the collisionality, modification of the magnetic field is required to achieve further control of the radial electric field, especially to produce a strong radial electric field shear. In the Large Helical Device (LHD) the radial electric field profiles are shown to be controlled by the modification of the magnetic field by (1) changing the radial profile of the effective helical ripples, ε h, (2) creating a magnetic island with an external perturbation field coil and (3) changing the local island divertor coil current.
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U2 - 10.1088/0029-5515/45/5/010
DO - 10.1088/0029-5515/45/5/010
M3 - Article
AN - SCOPUS:21144456717
VL - 45
SP - 391
EP - 398
JO - Nuclear Fusion
JF - Nuclear Fusion
SN - 0029-5515
IS - 5
ER -