Breeding blanket research

Development of breeding blanket for fusion reactors that produce tritium as fusion fuel, convert fusion energy into thermal energy, and shield neutrons to protect vacuum vessels and superconducting magnets

Concept of breeding blanket for DEMO (draft)

A. Research Objective

• Develop technologies for the design, manufacturing and operation of a breeding blanket system for DEMO, and research on advanced concepts.

B. Major Research Areas

• Research on design and manufacturing technology for the breeding blanket system
• Research on process and core equipment for the breeding blanket system
• Develop fusion materials and establish properties DB for the breeding blanket system
• Research on operation and maintenance technologies for the breeding blanket system

C. Expected Results

• Accomplish technological independence in fusion energy development and establish a foothold as a fast mover by securing breeding blanket technologies

Fuel cycle research

Development of processes and systems for fusion fuel supply, recovery, purification, separation, and storage, development of technology for tritium handling and management

ITER fuel cycle conceptual diagram

A. Research Objective

• Develop fusion fuel cycle design and manufacturing technology for DEMO

B. Major Research Areas

• Research on tracking fusion fuel cycle technology and development of safe tritium handling
• Research and development of tritium plant technology including deuterium: supply, recovery, purification, separation, storage and analysis technology

C. Expected Results

• Verification of large-scale tritium handling technology for fusion fuel (tritium) self-sufficiency for DEMO

Divertor research

Develop technology to maintain the high-performance core plasma by controlling impurities and helium ash in the extreme ultra-high temperature environment of the fusion reaction.

Diverter module for ITER (Procured from EU, Russia, Japan)

A. Research Objective

• Develop divertor design and manufacturing technology for DEMO
• Develop operating and maintenance technologies for divertor

B. Major Research Areas

• Divertor design and evaluation based on physics and engineering analyses
• Plasma facing material and manufacturing technology research
• Study on the effect of plasma-wall interaction on divertor

C. Expected Results

• Accomplish technology independence in fusion fuel system technology by acquiring own fusion reactor divertor design and manufacturing knowledge