Development of a tokamak reactor system code and its application for concept development of a demo reactor

Abstract

To develop the concept of a DEMO reactor, a tokamak reactor system analysis code has been developed at KAERI (Korea Atomic Energy Research Institute). The system analysis code incorporates prospects of the development of plasma physics and the technologies in a simple mathematical model and it helps to develop the concept of a DEMO reactor and to identify the necessary R&D areas for a realization of the concept. With the system analysis code, we investigated the performance of a DEMO reactor with a He cooled molten lithium (HCML) blanket as a tritium breeding blanket. It is shown that to access an operation space for a high electric power and for a steady-state operation, developments of improved method in both plasma physics and technology to handle a high heat load to a divertor and to increase the current drive efficiency are required.