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        Effect of Sips Sorption Isotherm on Contaminant Transport Mechanism in Fractured Porous Media

        Effect of Sips Sorption Isotherm on Contaminant Transport Mechanism,G. Suresh Kumara 대한토목학회 2016 KSCE Journal of Civil Engineering Vol.20 No.5

        A numerical model has been developed in this study for analysing the influence of Sips sorption isotherm on the contaminant transport mechanism in a coupled fracture matrix system. The implicit finite difference numerical technique has been used to solve the coupled non-linear governing equations. A varying grid is adopted at the fracture and rock matrix interface to capture the mass transfer at the interface. A constant continuous source of contaminants is assumed at the inlet of the fracture and the fracture is assumed to be saturated. Results suggest that the magnitude of the Sip’s equilibrium constant in the fracture is extremely sensitive in deciding the resultant transport behaviour within the high permeable fracture. The magnitude of the Sip’s model exponent within the high permeable fracture is highly sensitive in deciding the timing of zero concentration (exhaustion) within the high permeable fracture.

      • Perceptually Driven Visibility Optimization for Categorical Data Visualization

        Sungkil Lee,Sips, M.,Seidel, H-P IEEE 2013 IEEE transactions on visualization and computer gr Vol.19 No.10

        <P>Visualization techniques often use color to present categorical differences to a user. When selecting a color palette, the perceptual qualities of color need careful consideration. Large coherent groups visually suppress smaller groups and are often visually dominant in images. This paper introduces the concept of class visibility used to quantitatively measure the utility of a color palette to present coherent categorical structure to the user. We present a color optimization algorithm based on our class visibility metric to make categorical differences clearly visible to the user. We performed two user experiments on user preference and visual search to validate our visibility measure over a range of color palettes. The results indicate that visibility is a robust measure, and our color optimization can increase the effectiveness of categorical data visualizations.</P>

      • SCISCIESCOPUS

        Simulation of the hybrid and steady state advanced operating modes in ITER

        Kessel, C.E.,Giruzzi, G.,Sips, A.C.C.,Budny, R.V.,Artaud, J.F.,Basiuk, V.,Imbeaux, F.,Joffrin, E.,Schneider, M.,Murakami, M.,Luce, T.,St John, Holger,Oikawa, T.,Hayashi, N.,Takizuka, T.,Ozeki, T.,Na, International Atomic Energy Agency 2007 Nuclear fusion Vol.47 No.9

        <P>Integrated simulations are performed to establish a physics basis, in conjunction with present tokamak experiments, for the operating modes in the International Thermonuclear Experimental Reactor (ITER). Simulations of the hybrid mode are done using both fixed and free-boundary 1.5D transport evolution codes including CRONOS, ONETWO, TSC/TRANSP, TOPICS and ASTRA. The hybrid operating mode is simulated using the GLF23 and CDBM05 energy transport models. The injected powers are limited to the negative ion neutral beam, ion cyclotron and electron cyclotron heating systems. Several plasma parameters and source parameters are specified for the hybrid cases to provide a comparison of 1.5D core transport modelling assumptions, source physics modelling assumptions, as well as numerous peripheral physics modelling. Initial results indicate that very strict guidelines will need to be imposed on the application of GLF23, for example, to make useful comparisons. Some of the variations among the simulations are due to source models which vary widely among the codes used. In addition, there are a number of peripheral physics models that should be examined, some of which include fusion power production, bootstrap current, treatment of fast particles and treatment of impurities. The hybrid simulations project to fusion gains of 5.6–8.3, β<SUB>N</SUB> values of 2.1–2.6 and fusion powers ranging from 350 to 500 MW, under the assumptions outlined in section 3. Simulations of the steady state operating mode are done with the same 1.5D transport evolution codes cited above, except the ASTRA code. In these cases the energy transport model is more difficult to prescribe, so that energy confinement models will range from theory based to empirically based. The injected powers include the same sources as used for the hybrid with the possible addition of lower hybrid. The simulations of the steady state mode project to fusion gains of 3.5–7, β<SUB>N</SUB> values of 2.3–3.0 and fusion powers of 290 to 415 MW, under the assumptions described in section 4. These simulations will be presented and compared with particular focus on the resulting temperature profiles, source profiles and peripheral physics profiles. The steady state simulations are at an early stage and are focused on developing a range of safety factor profiles with 100% non-inductive current.</P>

      • SCISCIESCOPUS

        Simulations of KSTAR high performance steady state operation scenarios

        Na, Yong-Su,Kessel, C.E.,Park, J.M.,Yi, Sumin,Becoulet, A.,Sips, A.C.C.,Kim, J.Y. International Atomic Energy Agency 2009 Nuclear fusion Vol.49 No.11

        <P>We report the results of predictive modelling of high performance steady state operation scenarios in KSTAR. Firstly, the capabilities of steady state operation are investigated with time-dependent simulations using a free-boundary plasma equilibrium evolution code coupled with transport calculations. Secondly, the reproducibility of high performance steady state operation scenarios developed in the DIII-D tokamak, of similar size to that of KSTAR, is investigated using the experimental data taken from DIII-D. Finally, the capability of ITER-relevant steady state operation is investigated in KSTAR. It is found that KSTAR is able to establish high performance steady state operation scenarios; β<SUB>N</SUB> above 3, <I>H</I><SUB>98</SUB>(<I>y</I>, 2) up to 2.0, <I>f</I><SUB>BS</SUB> up to 0.76 and <I>f</I><SUB>NI</SUB> equals 1.0. In this work, a realistic density profile is newly introduced for predictive simulations by employing the scaling law of a density peaking factor. The influence of the current ramp-up scenario and the transport model is discussed with respect to the fusion performance and non-inductive current drive fraction in the transport simulations. As observed in the experiments, both the heating and the plasma current waveforms in the current ramp-up phase produce a strong effect on the <I>q</I>-profile, the fusion performance and also on the non-inductive current drive fraction in the current flattop phase. A criterion in terms of <I>q</I><SUB>min</SUB> is found to establish ITER-relevant steady state operation scenarios. This will provide a guideline for designing the current ramp-up phase in KSTAR. It is observed that the transport model also affects the predictive values of fusion performance as well as the non-inductive current drive fraction. The Weiland transport model predicts the highest fusion performance as well as non-inductive current drive fraction in KSTAR. In contrast, the GLF23 model exhibits the lowest ones. ITER-relevant advanced scenarios cannot be obtained with the GLF23 model in the conditions given in this work. Finally, ideal MHD stability is investigated for the ITER-relevant advanced scenarios in KSTAR. The methods and results presented in this paper are expected to contribute to improving the ITER and beyond ITER predictive simulations.</P>

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