Published February 2008 | Version v1
Journal article

Tokamak reactor system analysis code for the conceptual development of demo reactor

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

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 and 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

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
40
Journal Issue
1
Series
6 refs, 4 figs
Journal Page Range
p. 87-92
ISSN
1738-5733