Assessment of Spherical Tokamak Reactors Comparing with Other Fusion Power Plants
スポンサーリンク
概要
- 論文の詳細を見る
The 1-GWe D-T normal-conducting spherical tokamak (ST) reactor is designed using PEC (Physics-Engineering-Cost) system code, and is compared with conventional superconducting tokamak reactor (TR) and other fusion reactors. Especially two reference ST designs and one reference TR design are defined, and their design and environmental parameters are compared. It is found that the cost of electricity (COE), the life-cycle CO2 emission rate and the energy payback ratio (EPR) strongly depend on plasma aspect ratio in ST designs, in contrast to TR designs which are insensitive to plasma aspect ratio. The clarification of plasma beta and confinement improvement factor in ST plasmas is crucial for searching for optimized reactor designs.
- 2012-07-01
著者
-
NAGAYAMA Yoshio
National Insitute for Fusion Science
-
Yamazaki Kozo
Department Of Nuclear Engineering Faculty Of Engineering University Of Tokyo
-
Arimoto Hideki
Department Of Energy Engineering And Science Nagoya University
-
Oishi Tetsutarou
Department Of Quantum Engineering And System Science Graduate School Of Engineering The University O
-
Oishi Tetsutarou
Nagoya University
-
Nagayama Yoshio
National Institute For Fusion Science
-
Arimoto Hideki
Nagoya University
-
YAMAZAKI Kozo
Nagoya University
-
BAN Kanae
Department of Energy Engineering and Science, Nagoya University
-
KONDO Takuya
Department of Energy Engineering and Science, Nagoya University
-
Ban Kanae
Department Of Energy Engineering And Science Nagoya University
-
Kondo Takuya
Department Of Energy Engineering And Science Nagoya University
-
OISHI Tetsutarou
Department of Energy Engineering and Science, Graduate School of Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8093, Japan
-
OISHI Tetsutarou
Department of Energy Engineering and Science, Graduate School of Engineering, Nagoya University
-
YAMAZAKI Kozo
Department of Energy Engineering and Science, Graduate School of Engineering, Nagoya University
関連論文
- Stability and Confinement Studies of High-Performance NBI Plasmas in the Large Helical Device Toward a Steady-State Helical Fusion Reactor
- Achievement of 10 keV Central Electron Temperatures by ECH in LHD
- Local Impurity Deposition in a Magnetic Island by Means of a Tracer-Encapsulated Solid Pellet in the LHD
- Steady Burning Criteria for D-3He Spherical Tokamak Reactor with Internal Transport Barrier
- Transition of Edge Particle Transport in CHS
- Extension of Improved Particle and Energy Confinement Regime in the Core of LHD Plasma
- Clustered Data Storage for Multi-Site Fusion Experiments
- Experiments on Runaway Electrons in a Toroidal Plasma
- Second Order Effect of a High-β Tokamak Equilibrium
- Environmental and Economical Assessment of Various Fusion Reactors by the Calculation of CO2 Emission Amounts
- Analysis of Particle Orbits in a Spherical Tokamak-Stellarator Hybrid System (TOKASTAR) and Experiments in the Compact-TOKASTAR Device
- Transport Analysis of High-Z Impurities Including Sawtooth Effects in a Tokamak System
- Time-Dependent NBI-Heating Simulation of LHD Plasmas Using Toroidal Transport Analysis Linkage Code
- Internal Transport Barrier Formation and Pellet Injection Simulation in Helical and Tokamak Reactors
- Effect of Plasma Biasing on Suppression of Electrostatic Fluctuation in the Edge Region of STP-3(M) Reversed Field Pinch(Gases, Plasmas and Electric Discharges)
- Contribution of the Electrostatic Fluctuation to the Particle and Energy Fluxes in the Edge Region of STP-3 (M) Reversed Field Pinch Plasma (Gases, Plasmas and Electric Discharges)
- Maximum Entropy Analysis of the 2D Density Turbulence Measured by MIR in TPE-RX
- Analysis of Radiative Mantle Formation by Impurity Seeding in ITER
- Progress in Impurity-Related Physics Experiments in LHD
- Long Range Temperature Fluctuation in LHD
- Transport Dynamics and Multi-Scale Coupling of Turbulence in LHD
- Transmutation of High-level Wastes in a Spherical-tokamak Reactor
- Optics Design for Microwave Imaging Reflectometry in LHD
- Control of Neoclassical Tearing Mode by Electron Cyclotron Current Drive and Non-Resonant Helical Field Application in ITER
- Improved Data Acquisition Methods for Uninterrupted Signal Monitoring and Ultra-Fast Plasma Diagnostics in LHD
- Bi-Coherence Analysis of Fluctuations with Long Distance Correlation in Toroidal Plasmas
- Assessment of Spherical Tokamak Reactors Comparing with Other Fusion Power Plants
- Recent Progress on Microwave Imaging Technology and New Physics Results
- Life Cycle Assessment for Energy Payback of Spherical Tokamak Reactors
- A Conceptual Design of Superconducting Spherical Tokamak Reactor
- Development of Portal Web Pages for the LHD Experiment
- Integrated Analysis on the Current Profile and the Operational Scenario of D-^3He Spherical Tokamak Reactors
- Confinement Analysis of Spherical Tokamak-Stellarator Hybrid Configurations
- Low Aspect Ratio Plasma in Tokamak-Helical Hybrid Device TOKASTAR-2
- Neoclassical Tearing Mode Analysis in Spherical Tokamak Burning Plasmas
- Internal Transport Barrier Analysis Including Impurities in Tokamak and Helical Reactor Plasmas
- Nonstop Lose-Less Data Acquisition and Storing Method for Plasma Motion Images
- Simulation of the Fuel Isotope Effect on the Confinement Property in DT Fusion Reactors
- Design and Installation of a New Electron Cyclotron Emission Diagnostic Antenna in LHD
- Research on Economics and CO2 Emission of Magnetic and Inertial Fusion Reactors
- Experiments of Plasma Current Start-Up in Tokamak-Helical Hybrid Device TOKASTAR-2
- Confinement of ECH Plasmas and Effect of Electrode Biasing in TOKASTAR-2
- Construction and Plasma Initiation of the Tokamak-Helical Hybrid Device TOKASTAR-2
- Initial Plasma Confinement Experiments in Tokamak-Helical Hybrid Device TOKASTAR-2
- Broadband Multichannel Radiometer for ECE Measurements on KSTAR
- Identification of MHD Mode Structure using ECE and SX Measurements
- Characteristics of Radiating Collapse at the Density Limit in the Large Helical Device
- Effect of Ellipticity on Thermal Transport in ECH Plasmas in LHD
- Development of ECE Imaging System on LHD
- Microwave Imaging Reflectometry Experiment in TPE-RX
- Experiments of Tokamak Discharge and Simulation of Magnetic Field Configuration in Tokamak-Helical Hybrid Device TOKASTAR-2
- Analysis of Internal Transport Barrier Formation in Tokamak Reactor Plasmas
- Performance Improvement in Real-Time Mapping of Thomson Scattering Data to Flux Coordinates in LHD
- Critical Issues of Burning Plasma, Engineering, Economic and Environmental Assessments on Steady-State Fusion Reactors
- Comparative Study of Cost Models for Tokamak DEMO Fusion Reactors
- Self-Consistent Pressure and Current Profiles in High-Beta D-3He Tokamak Reactors
- Economical and Life-Cycle Energy Assessment of Magnetic Fusion Power Reactors
- Economic Evaluation of D-T, D-3He, and Catalyzed D-D Fusion Reactors
- Effect of Plasma Biasing on Suppression of Electrostatic Fluctuation in the Edge Region of STP-3(M) Reversed Field Pinch(Gases, Plasmas and Electric Discharges)