Conceptual Design of Fast Ignition Power Plant KOYO-F Driven by Cooled Yb:YAG Ceramic Laser

@article{Norimatsu2007ConceptualDO,
  title={Conceptual Design of Fast Ignition Power Plant KOYO-F Driven by Cooled Yb:YAG Ceramic Laser},
  author={Takayoshi Norimatsu and Junji Kawanaka and Miki Miyanaga and Hiroshi Azechi and K. Mima and Hiroyuki Furukawa and Yasuji Kozaki and Ken Tomabechi},
  journal={Fusion Science and Technology},
  year={2007},
  volume={52},
  pages={893 - 900}
}
Abstract Recent progress on fast ignition (FI) and cooled Yb:YAG ceramic laser enable us to design an IFE power plant with a 1MJ-class, compact laser whose output energy is 1/4 of previous central ignition scheme. Basing on the FI scheme, we conceptually designed a laser fusion power plant driven with cooled-Yb:YAG, ceramic lasers. The cooled Yb-YAG ceramic was newly chosen as the laser material. We found that the heating laser for ignition could be constructed with the cooled Yb:YAG ceramics… 
11 Citations
Conceptual design of a subcritical research reactor for inertial fusion energy with the J-EPoCH facility
Abstract The Japan Establishment for a Power-laser Community Harvest (J-EPoCH) is proposed as a next generation laser facility having multi-purpose high repetition laser beams at the maximum rate of
Relaxation of Surface Tension Waves on a Liquid Metal Mirror for a Fast-Ignition Laser Fusion Plant
Abstract A grazing incidence, shallow liquid metal mirror could be used as the final optic for the heating laser in a fast-ignition fusion power plant. The relaxation of vibrations on the surface of
1-Hz Bead-Pellet Injection System for Fusion Reaction Engaged by a Laser HAMA Using Ultra-Intense Counter Beams
Abstract The injection and engagement of pellets using laser beam irradiation is one of the key technologies to realize a laser-driven inertial fusion energy (IFE) reactor. We irradiated
Leakage Control of Tritium Through Heat Cycles of Conceptual-Design, Laser-Fusion Reactor KOYO-F
Abstract To reduce the tritium permeation from the primary liquid metal loop to the secondary water loop, a heat exchanger concept that incorporates small diameter tubes containing an oxidizer was
Numerical Study for a Protection of Laser Beam Port by Magnetic Fields in the Laser Fusion Reactor KOYO-F
A possible method for protecting beam ports from alpha particles which are produced by a nuclear fusion in the Fast Ignition Laser Fusion Power Plant (KOTO-Fast) is proposed. A simple dipole magnetic
Numerical Study for Laser Source Protection from Alpha Particles by Magnetic Fields in a Laser Fusion Reactor
A possible method for protecting beam ports and laser sources from alpha particles which are produced by a nuclear fusion in the fast ignition laser fusion power plant (KOYO-Fast) is proposed. Two
Condensed hydrogen for thermonuclear fusion
Inertial confinement fusion (ICF) power, in either pure fusion or fission-fusion hybrid reactors, is a possible solution for future world’s energy demands. Formation of uniform layers of a condensed
Plasma irradiation experiment on the metal pebble flow in the TPDsheet-U
Abstract A new divertor concept REVOLVER-D2 that uses metal pebbles as a divertor target has been proposed for the LHD-type helical fusion reactor FFHR-c1. Demonstration of sufficient plasma
Proposal of an MFE-IFE cooperative system for a steady-state tritium balance
Abstract A new concept of a fusion reactor system, MFE-IFE cooperative system, is proposed. This concept combines the merits of a small-size MFE reactor and a dry-wall IFE reactor and aims at
3D CAD-MCNP Methodology Applied to Neutronic Irradiation Effects Analysis in KOYO-F
Abstract This paper presents a methodology for 3D neutronic calculations suitable for complex and extensive geometries. The geometry of the system design is first fully modeled with a CAD program;
...
1
2
...

References

SHOWING 1-10 OF 13 REFERENCES
Power Plant Concepts and Chamber Issues for Fast Ignition Direct-Drive Targets
Abstract We have analyzed the design windows for laser fusion power plants based on direct-drive fast ignition concepts and have examined the issues of chamber technologies and the feasibility of a
Nuclear fusion: Fast heating scalable to laser fusion ignition
TLDR
A refinement of this system in which a much more powerful, pulsed petawatt (1015 watts) laser creates a fast-heated core plasma that is scalable to full-scale ignition, significantly increasing the number of fusion events while still maintaining high heating efficiency at these substantially higher laser energies.
Dramatically improved laser characteristics of diode-pumped Yb-doped materials at low temperature
Dramatic improvements in the laser characteristics of ytterbium-doped materials were experimentally shown by cooling an ytterbium-doped laser crystal at low temperature. Quantum-defect-limited
Nd3+:YGdO3 ceramic laser
A highly transparent Nd 3+ :YGdO 3 ceramic solid-state laser material was developed using nanocrystalline technology and a nonpress vacuum sintering method. Spectroscopic properties of this ceramic
Efficient Active-Mirror Laser Oscillator with a Cooled Yb:YAG Ceramics
30W active-mirror oscillator with a liquid-nitrogen-cooled Yb:YAG ceramics has been demonstrated in quasi-cw diode pump. The optical efficiency and slope efficiency were high at 62% and 71%,
Condensation of Gases during Cryopumping—The Effect of Surface Temperature on the Critical Energy for Trapping
The critical energy for trapping was defined and was then calculated for five gases (N2, Ar, CO, CO2, and N2O). The gas and the solid on which it is trapped were of the same chemical species. The
Fluid Dynamic Aspects of the Porous Wetted Wall Protection Scheme for Inertial Fusion Energy Reactors
A numerical and experimental investigation has been conducted to analyze the fluid dynamic aspects of the porous wetted wall protection scheme for inertial fusion energy (IFE) reactor first walls. A
Thermal coefficients of the expansion and refractive index in YAG.
TLDR
The thermal expansion coefficient and dn/dT are measured by interferometry techniques in undoped YAG below 300 K by finding the coefficient at 125 K to be higher than that at 300 K.
Advanced Solid-State Photonics (OSA topical meeting, ASSP2006)
  • 2006
Simulation on Ablation for Design of Liquid Wall Chamber of Laser Fusion Reactor
  • J. Plasma and Fusion Res
  • 2006
...
1
2
...