Development of Integrated SOL/Divertor Code and Simulation Study in JAEA
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概要
- 論文の詳細を見る
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 effciency on the divertor geometry and operational conditions. The effciency is determined by the balance between the incident and back-flow fluxes into and from the exhaust chamber.
著者
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KAWASHIMA Hisato
Japan Atomic Energy Research Institute
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TAKIZUKA Tomonori
Japan Atomic Energy Research Institute
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Sakurai Shinji
Japan Atomic Energy Agency
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OZEKI Takahisa
Japan Atomic Energy Agency
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ASAKURA Nobuyuki
Japan Atomic Energy Agency
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SHIMIZU Katsuhiro
Japan Atomic Energy Agency, 801-1 Mukoyama, Naka 311-0193, Japan
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NAKANO Tomohide
Japan Atomic Energy Agency
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SHIMIZU Katsuhiro
Japan Atomic Energy Agency
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KAWASHIMA Hisato
Japan Atomic Energy Agency
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TAKIZUKA Tomonori
Japan Atomic Energy Agency
関連論文
- Impurity Behavior during the H-Mode in JFT-2M
- Ion Bernstein Wave Experiment on JFT-2M Tokamak
- Enhancement of Wall Fueling and Improvement in nτ of a Beam-Heated H-Mode Discharge by Electron Cyclotron Wave in the JFT-2M Tokamak
- Measurement of Peripheral Electron Temperature by Electron Cyclotron Emission during the H-Mode Transition in JFT-2M Tokamak
- Scrape-off Layer Plasma Flow in L- and H-Mode Plasmas on JT-60U
- Steady-State Operation Scenario and the First Experimental Result on QUEST
- Initial Boronization of JT-60U Tokamak Using Decaborane
- Fast Ion Loss Measurement by IRTV in a Reduced Ripple Experiment with Ferritic Inserts on JFT-2M
- Hollow Density Profile on Electron Cyclotron Resonance Heating JFT-2M Plasma
- Study of Runaway Electron Transport in Edge Stochastic Magnetic Field in the JFT-2M Tokamak
- Measurement of Anisotropic Soft X-Ray Emission during Radio-Frequency Current Drive in the JFT-2M Tokamak
- Edge Pedestal During the H-Mode of a Tokamak Plasma Measured by the Electron Cyclotron Emission
- Radial Distribution of the Plasma Current Driven by Lower-Hybrid Waves in the JFT-2M Tokamak
- Diamagnetic Measurement of JFT-2 Plasma Heated by Neutral Beam Injection
- Thermal Load Test of a TiC Coated Mo Limiter during Steady State and Major Current Disruption Phases in the JFT-2 Tokamak with Neutral Beam Injection
- Thomson Scattering Apparatus for Simultaneous Six-Position Measurements in the JFT-2 Tokamak
- Electron Thermal Diffusivity in JFT-2 Tokamak with NBI Heating
- Conceptual Design of Divertor Cassette Handling by Remote Handling System of JT-60SA
- Effect of Magnetic Island Associated with Neoclassical Tearing Modes on Plasma Rotation in JT-60U
- Electron Parallel Heat Transport in the Scrape-off Layer Using a Particle-in-Cell Code
- MHD Computations at JAERI : Extended Abstract of MHD Computations at JAERI / Extended Abstract of Numerical Study of Resistive Internal Kink Mode / Extended Abstract of Finite-Beta Effect on Tearing Mode
- Kinetic Particle Simulation Study of Parallel Heat Transport in Scrape-off Layer Plasmas over a Wide Range of Collisionalities
- Electron Diffusion in a Tokamak Due to High n-Ballooning Mode
- A Study of Particle Confinement Using Skin Radiative Approximation Method in JT-60 Tokamak
- Development of Flexible Neutron-Shielding Resin as an Additional Shielding Material
- Rotational Stabilization of Resistive Wall Mode on JT-60U
- Fractofusion Mechanism
- Spatial Structure of Volume Recombination in JT-60U Detached Divertor Plasmas
- X-Ray Spectra from Neon-like Tungsten Ions in the Interaction with Electrons
- Integrated Modeling of Whole Tokamak Plasma
- Blanket Concept of Water-Cooled Lithium Lead with Beryllium for the SlimCS Fusion DEMO Reactor
- Study of Plasma Current Decay in the Initial Phase of High Poloidal Beta Disruptions in JT-60U
- Numerical Method for the Stability Analysis of Ideal MHD Modes with a Wide Range of Toroidal Mode Numbers in Tokamaks
- Transient Response of Divertor Plasma During Transition to ELM Free H-Mode Phase in JT-60U
- Development of Integrated SOL/Divertor Code and Simulation Study in JAEA
- Control of Growth of Neoclassical Tearing Mode by Central Co-ECCD in JT-60U
- Offset Linear Scaling for H-mode Confinement.
- Comparison of Coolant Conditions in the Blanket for a Water-Cooled DEMO Reactor SlimCS
- Dynamics of Plasma during the Formation of a Weak Negative Central Magnetic Shear Configuration Using Counter Neutral Beam Injection in the JFT-2M Tokamak.