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Featured researches published by N. Ramasubramanian.


Plasma Physics and Controlled Fusion | 2001

First island divertor experiments on the W7-AS stellarator

P. Grigull; K. McCormick; J. Baldzuhn; R. Burhenn; R. Brakel; H. Ehmler; Y. Feng; F. Gadelmeier; L. Giannone; D. Hartmann; D. Hildebrandt; M. Hirsch; R. Jaenicke; J. Kisslinger; J. Knauer; R. König; G. Kühner; H. P. Laqua; D. Naujoks; H. Niedermeyer; N. Ramasubramanian; N. Rust; F. Sardei; F. Wagner; A. Weller; U. Wenzel

1. Abstract In the past, under limiter conditions, it has been impossible to produce high-power, highdensity, quasi-stationary neutral beam injection (NBI) discharges in W7-AS. Such discharges tended to evince impurity accumulation, lack of density control and subsequent radiation collapse (Normal Confinement). Presently, W7-AS is operating with a modular, open island divertor similar to that foreseen for W7-X. The divertor enables access to a new NBI heated, high density (ne up to 4·10 20 m -3 ) operating regime (High Density H-mode). It is extant above a threshold density, and is characterized by flat density profiles, high energyand low impurity confinement times and edge-localized radiation. The HDH-mode shows strong similarity to ELM-free H-mode scenarios previously observed in W7-AS, but in contrast to these avoids impurity accumulation. These new features enable full density control and quasi steady-state operation over many confinement times (at present only technically limited by the availability of NBI) also under conditions of partial detachment from the divertor targets. In HDH-mode, even in attached discharges, the divertor target load is considerable reduced. This is mainly due to favourable upstream conditions (higher nes), edge localized radiation and increased power deposition width. The benefits of the HDH-mode do not restrict only to hydrogen plasmas. They also occur ‐ albeit in a modified manner ‐ in deuterium plasmas. Undoubtedly, there are clear isotope effects between hydrogen and deuterium discharges. The results obtained in W7-AS render good prospects for W7-X and support the island divertor concept as a serious candidate for devices with magnetic islands at the edge. 2. Results Fig. 1 summarizes the behaviour of the energy confinement time E =W/Pabs, the normalized radiated power Prad/Pabs, and separatrix density nes obtained from quasi-stationary discharges with Pabs=1.4 MW as a function of the line-averaged density ne. E-values in NC follow the scaling E ISS95 =0.26· a 0.4 ·Bt 0.83 ·a 2.21 ·R 0.65 ·ne 0.51 ·Pabs -0.59 , [2], whereas for the HDH-mode one finds E ~ 2· E ISS95 . P rad /P abs grows smoothly with ne until partial plasma detachment, where a jump in the normalized radiated power occurs. The separatrix density n es increases sharply at the NC HDH-mode transition point, then continues to climb with ne and saturates


Journal of Nuclear Materials | 2003

Influence of magnetic field configurations on divertor plasma parameters in the W7-AS stellarator

P. Grigull; K. McCormick; Y. Feng; A. Werner; R. Brakel; H. Ehmler; F. Gadelmeier; D. Hartmann; D. Hildebrandt; R. Jaenicke; J. Kisslinger; T. Klinger; R. König; D. Naujoks; H. Niedermeyer; N. Ramasubramanian; F. Sardei; F. Wagner; U. Wenzel

Abstract The new island divertor in W7-AS enables quasi steady-state operation with NBI at very high density including scenarios with stable detachment from the targets. Experiments with reversed B-field indicate that the interaction zones on the targets are affected in first order by E×B drifts. Stable detachment is restricted to magnetic field configurations with sufficiently large separation between x-points and targets and not too small field line pitch inside the islands. It is always partial in the sense that it does not extend over the full target area. This inhomogeneity is ascribed to an in/out asymmetry of the electron temperature at the upstream separatrix position.


Nuclear Fusion | 2005

Physics of the geometry-related detachment stability in W7-AS

Y. Feng; F. Sardei; J. Kisslinger; P. Grigull; K. McCormick; D. Reiter; L. Giannone; R. König; N. Ramasubramanian; H. Thomsen; U. Wenzel

This paper presents a detailed analysis of the transport behaviour of the detached plasmas in W7-AS based on an extended numerical study using the EMC3-EIRENE code, aimed at understanding the underlying physics responsible for the geometry-dependent detachment stability observed in W7-AS island divertor experiments. Here, a stable detachment can only be established when the control coils are switched on to generate sufficiently large islands with relatively short connection lengths. Special attention will be paid to a discussion of the carbon radiation, location and dynamics of the radiation layer, the neutral screening efficiency specific to the island divertor geometry and its impact on the detachment stability. Based on the three-dimensional simulation results, a linear stability model is presented in order to obtain some insight into the mechanisms driving the instability. The radiation behaviour and the location and evolution of the radiation zone in the island divertor will be discussed with respect to those of tokamak-MARFEs.


Nuclear Fusion | 2009

Comparative divertor-transport study for helical devices

Y. Feng; M. Kobayashi; F. Sardei; S. Masuzaki; J. Kisslinger; T. Morisaki; P. Grigull; H. Yamada; K. McCormick; N. Ohyabu; R. König; I. Yamada; L. Giannone; K. Narihara; U. Wenzel; S. Morita; H. Thomsen; J. Miyazawa; N. Ramasubramanian; T. Watanabe; N. Ashikawa; K. Ida; A. Komori; O. Motojima; Y. Nakamura; B.J. Peterson; K. Sato; M. Shoji; Noriko Tamura; M. Tokitani

Using the island divertors (IDs) of W7-AS and W7-X and the helical divertor (HD) of LHD as examples, the paper presents a comparative divertor transport study for three typical helical devices of different machine sizes following two distinct divertor concepts, aiming at identifying common physics issues/effects for mutual validation and combined studies. Based on EMC3/EIRENE simulations supported by experimental results, the paper first reviews and compares the essential transport features of the W7-AS ID and the LHD HD in order to build a base and framework for a predictive study of W7-X. The fundamental role of low-order magnetic islands in both divertor concepts is emphasized. Preliminary EMC3/EIRENE simulation results for W7-X are presented and discussed with respect to W7-AS and LHD in order to show how the individual field and divertor topologies affect the divertor transport and performance. For instance, a high recycling regime, which is absent from W7-AS and LHD, is predicted to exist for W7-X. The paper focuses on identifying and understanding the role of divertors for high density plasma operations in helical devices. In this regard, special attention is paid to investigating the divertor function for controlling intrinsic impurities. Impurity transport behaviour and wall-sputtering processes of CX-neutrals are studied under different divertor plasma conditions. A divertor retention effect on intrinsic impurities at high SOL collisonalities is predicted for all the three devices. The required SOL plasma conditions and the underlying mechanisms are analysed in detail. Numerical results are discussed in conjunction with the experimental observations for high density divertor plasmas in W7-AS and LHD. Different SOL transport regimes are numerically identified for the standard divertor configuration of W7-X and the possible consequences on high density plasmas are assessed. All the EMC3-EIRENE simulations presented in this paper are based on vacuum fields and comparisons with local diagnostics are made for low-s plasmas.


symposium on fusion technology | 2003

Divertor operation in stellarators: results from W7-AS and implications for future devices

P. Grigull; K. McCormick; H. Renner; S. Masuzaki; R. König; J. Baldzuhn; S. Bäumel; R. Burhenn; R. Brakel; H. Ehmler; Y. Feng; F. Gadelmeier; L. Giannone; D. Hartmann; D. Hildebrandt; M. Hirsch; R. Jaenicke; J. Kisslinger; T. Klinger; J. Knauer; D. Naujoks; H. Niedermeyer; E. Pasch; N. Ramasubramanian; F. Sardei; F. Wagner; U. Wenzel; A. Werner; W As Team

The research on divertors for stellarators is at the beginning. Extensive studies are being prepared on large helical device (LHD) and W7-X. W7-AS is now being operated with an open island divertor (ID) which serves as a test bed for the W7-X diverter. The divertor enables access to a new NBI-heated, high-density operating regime with improved confinement properties. This regime-the high-density H-mode (HDH)-displays no evident mode activity, is extant above a threshold density and characterized by flat density profiles. high-energy- and low-impurity-confinement times and edge-localized radiation. Impurity accumulation, normally associated with ELM-free H-modes, is avoided. Quasi-steady-state discharges with n e up to 4 x 10 20 m -3 , edge radiation levels up to 90% and plasma partial detachment at the divertor targets can be simultaneously realized. The accessibility to other improved confinement modes in W7-AS (conventional H-mode anti OC-mode) is not restricted by the divertor. The results provide a promising basis for future experiments, in particular on W7-X, and recommend the ID as a serious candidate for solving the plasma exhaust problem in stellarators.


Nuclear Fusion | 2004

Radiative condensation and detachment in Wendelstein 7-AS stellarator

H. Thomsen; R. König; Y. Feng; P. Grigull; T. Klinger; K. McCormick; N. Ramasubramanian; U. Wenzel; W As Team

In the Wendelstein 7-AS stellarator (Renner et al 1989 Plasma Phys. Control. Fusion 31 1579), under particularly high plasma densities, a non-stationary radiation zone is observed to be formed on the inboard side of the torus. It causes a degradation of the diamagnetic energy of up to 50%. The configurational aspects of the magnetic field influence the development of the radiation zone as follows. The critical density is related to the connection length of the magnetic field, i.e. the observed degradation sets in at lower densities for magnetic configurations with large connection lengths. From camera observations, in conjunction with forward calculations, it is found that the radiation zone is located on closed field lines and forms a toroidal belt. Based on complementary observations, it is concluded that the radiation zone is caused by a radiative condensation instability (or multi-faceted asymmetric radiation from the edge). Fluctuations of the radiation zone were recorded using a fast framing camera with a time resolution of 25 µs. Temporal variations as well as spatial movements were observed. The fluctuations were found on various lines-of-sight around the torus with correlation and phase shifts compatible with a toroidal propagation.


Plasma Physics and Controlled Fusion | 2003

Bolometer tomography at the density limit of the HDH mode in the W7-AS stellarator

L. Giannone; R. Brakel; R. Burhenn; H. Ehmler; Y. Feng; P. Grigull; K. McCormick; F. Wagner; J. Baldzuhn; Y. Igitkhanov; J. Knauer; K Nishimura; E. Pasch; B J Peterson; N. Ramasubramanian; N. Rust; A. Weller; A. Werner

The installation of divertor plates in the W7-AS stellarator has allowed attainment of a high energy confinement regime at high density, where the radiation profiles reached steady state. In this regime, the radial profile of the radiated power is hollow. Raising the density to the point where the radiated power approached the input power led to plasma detachment and a decrease in diamagnetic energy. This defines the density limit in a stellarator and a scaling law for this maximum density can be heuristically derived on the basis of power balance considerations. The installation of two bolometer cameras away from the divertor plates and three bolometer cameras in the vicinity of the divertor plates has provided insight into the features of high density operation of a divertor in a stellarator. In the main chamber, tomographic inversion at the density limit has shown that a poloidally asymmetric radiation profile developed as the density limit was approached. In the divertor, radiation in front of the divertor plates occurred while the plasma was attached and this radiation zone vanished at plasma detachment. Steady state discharges of up to 1.5 s have been achieved for neutral beam injection power of up to 2 MW. A precursor to a spontaneous transition out of the high confinement regime has been identified.


Journal of Nuclear Materials | 2003

A new plasma condensation phenomenon in the W7-AS island divertor

U. Wenzel; K. McCormick; N. Ramasubramanian; P. Grigull; R. König

Abstract In the W7-AS stellerator with island divertor very high densities can be achieved in the high-density H-mode. As a consequence, the plasma in the divertor detaches as previously shown by the reduction of the particle flux at some strike point positions and an upward movement of the ionisation front. Our spectroscopic measurements prove the simultaneous formation of a high-density (8×1020 m−3), low temperature (0.2 eV) region at the detachment transition in the divertor on top. This plasma is strongly recombining, as a result a strong up/down pressure asymmetry develops. Since flux amplification at the strike points was not found in the island divertor, we suppose that a nonlinear thermal condensation instability leads to the observed high-density region.


Nuclear Fusion | 2004

Study of the detachment phases in the Wendelstein 7-AS stellarator

U. Wenzel; K. McCormick; N. Ramasubramanian; F. Gadelmeier; P. Grigull; R. König; H. Thomsen

An experimental overview of the detachment process in the W7-AS stellarator with island divertors is given. Results of different spectroscopic methods are combined with those of Langmuir probes and neutral pressure measurements. Two phases of the detachment process are identified: the detachment transition due to the unstable range of the radiative loss function of carbon and a volume recombination phase for densities well above those needed for the onset of detachment. The first phase is characterized by a sudden drop in the temperature at the plasma edge and in the divertor. As a consequence, the particle fluxes at the divertor targets on top and at the bottom are reduced to a different degree, depending on the region. In the second phase, the plasma between the strike lines in the upper divertor is strongly recombining. Simultaneously, a strong carbon radiation belt is observed in the inboard scrape-off layer. The physical mechanisms of both phases are discussed.


Review of Scientific Instruments | 2003

Island divertor spectroscopy at the Wendelstein W7-AS stellarator

R. König; N. Ramasubramanian; K. McCormick; P. Grigull; F. Gadelmeier; U. Wenzel; B. Schweer; M. Brix

The island divertor concept, which is regarded as being the natural concept for low shear advanced stellarators like W7-AS and W7-X, has for the first time been put to a realistic test in the present experimental campaign of W7-AS. A large number of diagnostics, specifically geared towards the diagnosis of island divertor plasmas, have been installed in the course of the last two years. This report will introduce some of the newly installed active and passive spectroscopy based divertor diagnostics.

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