A Robust Design Window for the Heliotron DEMO Reactors
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概要
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According to the achievements in the Large Helical Device (LHD) experiments, a design of a DEMO reactor with a LHD-type heliotron system is foreseeable. On the other hand, a DEMO is the next step reactor and high reliability and feasibility are demanded in its design. In this study, a robust design window, i.e., the design window that is not sensitive to a change in uncertain physics parameters, was surveyed through parametric scans using a system design code. It was found that a difference in main design parameters (major radius, magnetic field strength, fusion output) gives only a small change in a dependence of physics requirements on the physics conditions. Therefore, it is important to find the design window with a lower requirement on the confinement improvement to assure the design robustness. In this respect, a reduction in the minimum inboard blanket space, one of the key parameters in a LHD-type heliotron reactor design, can effectively expand the design window and contributes to the design robustness. An acceptance of higher neutron wall load and an achievement of further high confinement improvement are also expected to make both a DEMO and a commercial reactor to be more feasible and economically attractive.
著者
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SAGARA Akio
National Insitute for Fusion Science
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MIYAZAWA Junichi
National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292, Japan
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YANAGI Nagato
National Institute for Fusion Science
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GOTO Takuya
National Institute for Fusion Science, Toki 509-5292 Japan
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TANAKA Teruya
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu 509-5292, Japan
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TANAKA Teruya
National Institute for Fusion Science
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GOTO Takuya
National Institute for Fusion Science
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MIYAZAWA Junichi
National Institute for Fusion Science
関連論文
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- Comparative Study on Effect of Boronization and Titanium Gettering in Compact Helical System Heliotron/Torsatron Device
- Retention and Desorption of Hydrogen and Helium in Inner Wall Material Used for The Large Helical Device (LHD) : Simulation experiments using a glow discharge apparatus
- Extension of Improved Particle and Energy Confinement Regime in the Core of LHD Plasma
- Dynamic Simulation of Erosion and Redeposition Patterns and Impurity Depth Profile of an LHD Divertor Plate
- Possibility of Profile Control using Compact Toroid Injection on Large Helical Device
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- Impurity Deposition and Retention of Discharge Gas on Plasma Facing Wall in LHD
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- Levitation Experiment Using a High-Temperature Superconductor Coil for a Plasma Confinement Device(Superconductors)
- Conceptual Design and Development of an Indirect-cooled Superconducting Helical Coil in the FFHR
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- Microstructures and Deuterium-Retention Behavior of Tungsten Exposed to D+(He and/or Be) Mixture Plasmas
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