Abstract

Large Helical Device (LHD) is one of the world largest superconducting fusion experiment devices, having demonstrated its inherent advantage for steady-state operation since the start of experiments in 1998. LHD has also demonstrated reliable operation of the large-scale superconducting magnet system for almost two decades. Development of the challenging heating systems, such as negative-ion-based neutral beam injection (NBI), high-power and high-frequency electron cyclotron heating, and steady-state ion cyclotron heating, have led to wide-ranging physics and engineering achievements. LHD has progressed to the next stage, that is, the deuterium experiment starting in March 2017, which should further extend plasma parameters toward reactor-relevant regime. For establishing firm basis for designing steady-state helical fusion reactor, advanced physics research, such as on isotope effect, energetic particle confinement, and plasma–wall interaction, will be intensively performed in the deuterium experiments. In an engineering aspect, the upgrade of NBI system has been carried out in preparation to the deuterium experiment, and it should contribute to future NBI development for fusion reactors including ITER. For enhancement of the particle control, the closed divertor system has been installed with pumping capability. Diagnostics for neutron measurements are newly developed and installed for the deuterium experiment. Aligned with all the progress of LHD project in terms of engineering and physics aspects, the conceptual design activity of the LHD-type helical fusion reactor, FFHR-d1, has been programmatically conducted. In parallel to the design study, engineering research and development for the component development have been performed, including those based on employing challenging ideas such as high-temperature superconductor, liquid metal ergodic divertor, and molten-salt breeder blanket. The present status of LHD project entering the deuterium experiment phase is overviewed with putting emphasis on the engineering aspects, and then the engineering research and development activities toward steady-state helical fusion reactor are described.

Highlights

  • Aligned with all the progress of Large Helical Device (LHD) project in terms of engineering and physics aspects, the conceptual design activity of the LHD-type helical fusion reactor, FFHR-d1, has been programmatically conducted

  • LHD is equipped with three kinds of heating systems, NBI system [2]

  • It should further extend these parameters towards reactorrelevant regime, in which advanced research can be performed for establishing firm basis for designing steady-state helical fusion reactor

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Summary

INTRODUCTION

He Large Helical Device (LHD) is one of the world largest superconducting helical devices. The LHD, as the one of helical experiment devices, has played complementary and alternative roles to tokamak approach, and made progress on comprehend physics understandings of toroidal plasmas and on establishing scientific basis for a helical fusion reactor. High-performance and steady-state plasmas are required to realize fusion reactor. Tokamaks should achieve steady-state operation keeping its high plasma performance. It should further extend these parameters towards reactorrelevant regime, in which advanced research can be performed for establishing firm basis for designing steady-state helical fusion reactor. The. Key plasma parameters (Ti: ion temperature, Te: electron temperature, electron density, beta value, and steady-state operation) achieved in LHD (hydrogen plasma experiment phase) are summarized along with the relevant key physics and the target values of these parameters

Large-Scale Superconducting Magnets System
Heating Systems
Closed Helical Divertor
Tritium Removal System
LHD ENTERING THE DEUTERIUM EXPERIMENT PHASE
Findings
CONCLUDING REMARKS
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