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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2008.1
- 수록면
- 87 - 92 (6page)
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초록· 키워드
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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.
목차
등록된 정보가 없습니다.
참고문헌 (6)
참고문헌 신청
/ 1999 / ITER Physics Basis / Nucl. Fusion 39 : 2175 ~
/ 2007 / ITER Physics Basis / Nucl. Fusion 47 : 1 ~
F. Troyon / 1984 / Plasma Physics and Controlled / Fusion 26 : 209 ~
N. Koizumi / 2002 / Cryogenics 42 : 675 ~
Y. Kim / 2005 / A Neutronic Investigation of He-cooled Liquid Li-breeder Blankets for Fusion Power Reactor / Fusion Eng. and Design : 75 ~ 79
/ 2007 / ITER Physics Basis / Nucl. Fusion 47 : 1 ~
F. Troyon / 1984 / Plasma Physics and Controlled / Fusion 26 : 209 ~
N. Koizumi / 2002 / Cryogenics 42 : 675 ~
Y. Kim / 2005 / A Neutronic Investigation of He-cooled Liquid Li-breeder Blankets for Fusion Power Reactor / Fusion Eng. and Design : 75 ~ 79
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