The structure of the edge radial electric field E r inferred from the poloidal rotation velocity is compared with that of the particle and thermal transport barrier for //-mode plasmas in JFT-2M. Both E r and its gradient dE r /dr in the thermal transport barrier are found to become more negative at the L-H transition. On the other hand, dE r /dr is more positive outside of the separatrix. The shear of the radial electric field and poloidal rotation velocity in the H mode is localized within the order of an ion poloidal gyroradius near the separatrix, in the region of ion collisionality v*, ~ 20-40.PACS numbers: 52.55. Fa, 52.55.Pi, 52.70.Kz Since the //-mode plasma was discovered in ASDEX, it has been observed in many tokamaks. 2 " 0 Several theoretical models on the transition from L-mode to Hmode plasmas have been presented. 6 " 11 Recently, a radial electric field (E r ) near the plasma periphery has been found both experimentally and theoretically to play an important role in the L-H transition. 12 " 19 A more negative radial electric field was observed a few ms before the L-H transition in DIII-D (Ref. 12), and a decrease in particle transport was observed with negative E r , by driving a radial current, in the Continuous Current Tokamak. 13 Theoretical models associated with the radial electric field have been proposed to explain the L-H transition. 14 " 17 However, the predicted change of the gradient of the radial electric field (dE r /dr) is different between the models. In Shaing and Crume's model, 16 the poloidal flow velocity changes at the L-H transition and the corresponding radial electric field E r becomes more negative and dE r /dr becomes more positive, hence suppressing the fluctuations. On the other hand, Itoh and Itorfs model 17 predicts positive values of dE r /dr in the L mode and negative values of dE r /dr in the H mode, and that this negative dE r /dr reduces the banana width of the ions and the electron anomalous flux by the improved microstability. Thus it is crucial to measure the gradient or profile of the radial electric field for Land //-mode plasmas in tokamaks.In this paper we present the radial electric-field profile and temperature gradient profile a few cm inside the separatrix where the transport barrier is produced in Hmode plasmas in JFT-2M. 5 The radial electric-field profiles are inferred from poloidal and toroidal rotation velocity profiles and ion pressure profiles using the ionmomentum-balance equation, eZ { n, orwhere Z,, /?,, and n, are the ion charge, pressure, and density, B^ and B e are the toroidal and poloidal magnetic fields, and i> and v e are the toroidal and poloidal rotation velocities. The toroidal rotation velocity, ion temperature, and fully stripped carbon density profiles are measured using a multichannel charge-exchangespectroscopy technique 18,19 at Cvi 5292 A with toroidal arrays (two sets of 34 channels) with a spatial resolution of 1 cm. The poloidal rotation velocity and edge ion temperature profiles are measured using the intrinsic radiat...

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The atomic and electronic structures of binary Li2S-P2S5 glasses used as solid electrolytes are modeled by a combination of density functional theory (DFT) and reverse Monte Carlo (RMC) simulation using synchrotron X-ray diffraction, neutron diffraction, and Raman spectroscopy data. The ratio of PSx polyhedral anions based on the Raman spectroscopic results is reflected in the glassy structures of the 67Li2S-33P2S5, 70Li2S-30P2S5, and 75Li2S-25P2S5 glasses, and the plausible structures represent the lithium ion distributions around them. It is found that the edge sharing between PSx and LiSy polyhedra increases at a high Li2S content, and the free volume around PSx polyhedra decreases. It is conjectured that Li+ ions around the face of PSx polyhedra are clearly affected by the polarization of anions. The electronic structure of the DFT/RMC model suggests that the electron transfer between the P ion and the bridging sulfur (BS) ion weakens the positive charge of the P ion in the P2S7 anions. The P2S7 anions of the weak electrostatic repulsion would causes it to more strongly attract Li+ ions than the PS4 and P2S6 anions, and suppress the lithium ionic conduction. Thus, the control of the edge sharing between PSx and LiSy polyhedra without the electron transfer between the P ion and the BS ion is expected to facilitate lithium ionic conduction in the above solid electrolytes.

The paper describes the content of an H-mode confinement database that has been assembled for the ITER project. Data were collected from six machines of different sizes and shapes: ASDEX, DIII-D, JET, JFT-2M, PBX-M and PDX. A detailed description of the criteria used in the selection of the data and the definition of each of the variables is given. The paper also presents an analysis of the conditions of the database, the scalings (power law and offset linear) of the data with both dimensional and dimensionless variables, and predictions of the expected confinement time for ITER.

This paper describes an update of the H mode confinement database that has been assembled for the ITER project. Data were collected from six machines of different sizes and shapes: ASDEX, DIII-D, JET, JFT-2M, PBX-M and PDX. The updated database contains better estimates of fast ion energy content and thermal energy confinement times, discharges with RF heating, data using boronization, beryllium and pellets, more systematic parameter scans, and other features. The list of variables in the database has been expanded, and the selection criteria for the standard dataset have been modified. We also present simple scalings of the total and thermal energy confinement time to the new dataset.