Impurity transport modelling and simulation analysis of impurity behavior in JT-60U

Shimizu, K.; Kubo, H.; Takizuka, T.; Azumi, M.; Shimada, M.; Tsuji, S.; Hosogane, N.; Sugie, Toshiharu; Sakasai, A.; Asakura, N.; Higashijima, S.

doi:10.1016/0022-3115(94)00499-4

Cited by 53 publications

(52 citation statements)

References 7 publications

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“…At this boundary, one might specify the heat flux crossing the surface from the confined plasma, the density and temperature. There are now several large plasma fluid codes used to model the edge, with the major ones being B2 [811][812][813], UEDGE [814][815][816], EDGE2D [817,818], PLANET [819], and UEDA [820].…”

Section: Two or Three-dimensional Fluid Modellingmentioning

confidence: 99%

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Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Section: Two or Three-dimensional Fluid Modellingmentioning

confidence: 99%

“…There are a number of impurity transport codes using the Monte-Carlo technique. These include WBC [830], DIVIMP [831], IMPMC [820] MCI [832] and BBQ [327,833].…”

Section: Two or Three-dimensional Fluid Modellingmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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“…In most 2D multi-fluid divertor codes [2][3][4], impurity transport is solved simultaneously as a fluid species. On the other hand, some elaborate Monte Carlo codes have been developed for the interpretation of impurity behavior in the divertor, e.g., DIVIMP [17] and IMPMC [6]. In these Monte Carlo codes, impurity transport is solved under the background plasma parameters obtained by a simple divertor code named the "Onion-Skin model" [18], in order to take full advantage of the available experimental data.…”

Section: Impmc Codementioning

confidence: 99%

“…We have been developing simulation codes originally, since physics models can be verified quickly and with flexibility under the circumstance of close collaboration with the JT-60 experimental team. Figure 1 shows our code system, which consists of the 2-dimensional fluid code SOLDOR [5], the neutral Monte Carlo code NEUT2D [5], and the impurity Monte Carlo code IMPMC [6]. The particle simulation code PARASOL [7] has also been developed in order to establish a physics modeling used in fluid simulations, such author's e-mail: kawashima.hisato@jaea.go.jp as the boundary condition at the divertor target and heat transport along the field line.…”

Section: Introductionmentioning

confidence: 99%

Development of Integrated SOL/Divertor Code and Simulation Study in JAEA

Kawashima

Shimizu

Takizuka

et al. 2006

Plasma and Fusion Research

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An integrated SOL/divertor code is being developed by the JAEA (Japan Atomic Energy Agency) for interpretation and prediction studies of the behavior of plasmas, neutrals, and impurities in the SOL/divertor region. A code system consists of the 2D fluid code for plasma (SOLDOR), the neutral Monte-Carlo code (NEUT2D), the impurity Monte-Carlo code (IMPMC), and the particle simulation code (PARASOL). The physical processes of neutrals and impurities are studied using the Monte Carlo (MC) code to accomplish highly accurate simulations. The so-called divertor code, SOLDOR/NEUT2D, has the following features: 1) a high-resolution oscillation-free scheme for solving fluid equations, 2) neutral transport calculation under the condition of fine meshes, 3) successful reduction of MC noise, and 4) optimization of the massive parallel computer. As a result, our code can obtain a steady state solution within 3 ∼ 4 hours even in the first run of a series of simulations, allowing the performance of an effective parameter survey. The simulation reproduces the X-point MARFE (multifaceted asymmetric radiation from edge) in the JT-60U. It is found that the chemically sputtered carbon at the dome causes radiation peaking near the X-point. The performance of divertor pumping in the JT-60U is evaluated based on particle balances. In regard to the divertor design of the next tokamak of JT-60U, the simulation indicates the dependencies of pumping efficiency on the divertor geometry and operational conditions. The efficiency is determined by the balance between the incident and back-flow fluxes into and from the exhaust chamber.

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“…The SOL/divertor model consists of transports of SOL/divertor plasmas and of neutrals and impurities, and thus should satisfy many difficult requirements, such as the complex geometry, the atomic and molecular processes of neutrals and impurities. To investigate the SOL/divertor physics, the integrated SOL/divertor code SONIC [8] has been developed by coupling the plasma fluid code SOLDOR [9], the neutral Monte Carlo (MC) code NEUT2D [10] and the impurity MC code IMPMC [11]. The SONIC also can deal with the edge/pedestal region when the core boundary is set inside the edge/pedestal region.…”

Section: Introductionmentioning

confidence: 99%

Integrated Modeling of Whole Tokamak Plasma

Hayashi

Honda

Hoshino

et al. 2011

Plasma and Fusion Research

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Development and integration of models for the whole tokamak plasma have progressed on the basis of experimental analyses and first principle simulations. Integrated models of core, edge-pedestal and scrape-offlayer (SOL)-divertor clarified complex and autonomous features of reactor relevant plasmas. The integrated core plasma model including an anomalous transport of alpha particles by Alfven eigenmodes is developed in the core transport code TOPICS-IB and indicates the degradation of fusion performance. The integrated rotation model is developed in the advanced transport code TASK/TX and clarifies the mechanism of alpha particle-driven toroidal flow. A transport model of high-Z impurities is developed and predicts large inward pinch in a plasma rotating in the direction counter to the plasma current. TOPICS-IB is extended to include the edge-pedestal model by integrating with the stability code, simple SOL-divertor and pellet models, and clarifies the mechanism of pellet triggered ELM. The integrated SOL-divertor code SONIC is further integrated with TOPICS-IB and enables to study and design operation scenarios compatible with both the high confinement in the core and the low heat load on divertor plates.

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Impurity transport modelling and simulation analysis of impurity behavior in JT-60U

Cited by 53 publications

References 7 publications

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Development of Integrated SOL/Divertor Code and Simulation Study in JAEA

Integrated Modeling of Whole Tokamak Plasma

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