Environmental and Economical Assessment of Various Fusion Reactors by the Calculation of CO2 Emission Amounts
スポンサーリンク
概要
- 論文の詳細を見る
We compared the CO2 emissions of several fusion reactors. The magnetic confinement systems evaluated here are the tokamak reactor (TR), helical reactor (HR), and spherical tokamak reactor (ST). These models are calculated by the Physics-Engineering-Cost (PEC) code. The inertial confinement fusion reactor (IR) is also evaluated, assuming its driver energy and driver efficiency. In addition, different blanket modules and fuels are considered in the TR designs. To calculate life-cycle CO2 emission from fusion reactors defined by plasma parameters and radial build, we used a basic unit for CO2 weights (kt-CO2/t-material). Calculation results indicate that CO2 is emitted mainly in the construction stage of superconducting magnet systems for magnetic confinement fusion reactors. For the IR design, the driver system construction and pellet fabrication stages involve considerable CO2 emission. By comparing fusion reactors with other electric power generation systems in terms of CO2 emission, we confirmed that fusion reactors emit less CO2. Therefore, introducing a carbon tax has little effect on the economics of fusion reactors, and the cost of electricity (COE) from fusion reactors might be lower than that of oil-fired electric power plants when a carbon tax of around several hundred yen/t-CO2 is introduced.
著者
-
Yamazaki Kozo
Department Of Nuclear Engineering Faculty Of Engineering University Of Tokyo
-
Shoji Tatsuo
Department Of Energy Engineering And Science Nagoya University
-
Arimoto Hideki
Department Of Energy Engineering And Science Nagoya University
-
Uemura Satoshi
Department Of Medical Science And Cardiorenal Medicine Yokohama City University School Of Medicine
-
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
-
UEMURA Satoshi
Department of Energy Engineering and Science, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan
関連論文
- Transition of Edge Particle Transport in CHS
- 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
- 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)
- Analysis of Radiative Mantle Formation by Impurity Seeding in ITER
- Axial Profile of Balmer-Alpha Emission near a Tungsten Target in the Compact PWI Simulator APSEDAS
- Progress in Impurity-Related Physics Experiments in LHD
- Studies on Magnetron Sputtering Assisted by Inductively Coupled RF Plasma for Enhanced Metal Ionization
- Ion Extraction Characteristics from Photoionized Plasma by Radio-Frequency Resonance Method
- New Method of Particle Confinement Time Measurement in RF Traps
- Effects of renal dysfunction on cardiovascular events in diabetic patients with hypertension : Challenge-DM Study subgroup analysis
- Plasma Production by m = 0 Standing Helicon Waves
- Production of Inductively-Coupled Large-Diameter Plasmas with Internal Antenna
- Compact High-Density Plasma Source Produced by Using Standing Helicon Waves
- Characterization of Plasma Production by $m=0$ Standing Helicon Waves
- Control of Neoclassical Tearing Mode by Electron Cyclotron Current Drive and Non-Resonant Helical Field Application in ITER
- Assessment of Spherical Tokamak Reactors Comparing with Other Fusion Power Plants
- 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
- Initial Plasma Confinement Experiments in Tokamak-Helical Hybrid Device TOKASTAR-2
- Experiments of Tokamak Discharge and Simulation of Magnetic Field Configuration in Tokamak-Helical Hybrid Device TOKASTAR-2
- Self-Consistent Pressure and Current Profiles in High-Beta D-3He Tokamak Reactors
- Studies on Magnetron Sputtering Assisted by Inductively Coupled RF Plasma for Enhanced Metal Ionization
- 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)