TOKAMAK REACTOR SYSTEM ANALYSIS CODE FOR THE CONCEPTUAL DEVELOPMENT OF DEMO REACTOR

다국어 초록 (Multilingual Abstract)

Tokamak reactor system analysis code was developed at KAERI (Korea Atomic Energy Research Institute) and is used
here for the conceptual development of a DEMO reactor. In the system analysis code, prospects of the development of plasma
physics and the relevant technology are included in a simple mathematical model, i.e., the overall plant power balance
equation and the plasma power balance equation. This system analysis code provides satisfactory results for developing the
concept of a DEMO reactor and for identifying the necessary R&D areas, both in the physics and technology areas for the
realization of the concept. With this system analysis code, the performance of a DEMO reactor with a limited extension of
the plasma physics and technology adopted in the ITER design. The main requirements for the DEMO reactor were selected
as: 1) demonstrate tritium self-sufficiency, 2) generate net electricity, and 3) achieve a steady-state operation. It was shown
that to access an operational region for higher performance, the main restrictions are presented by the divertor heat load and
the steady-state operation requirements.

참고문헌 (Reference)

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