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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2009.1
- 수록면
- 427 - 446 (20page)
이용수
초록· 키워드
오류제보하기
In order to meet the increasing demand for electricity, Korea has to rely on nuclear energy due to its poor natural resources. In
order for nuclear energy to be expanded in its utilization, issues with uranium supply and waste management issues have to be
addressed. Fast reactor system is one of the most promising options for electricity generation with its efficient utilization of uranium
resources and reduction of radioactive waste, thus contributing to sustainable development. The Korea Atomic Energy Research
Institute (KAERI) has been performing R&Ds on Sodium-cooled Fast Reactors (SFRs) under the national nuclear R&D program.
Based on the experiences gained from the development of KALIMER conceptual designs of a pool-type U-TRU-10%Zr metal fuel
loaded reactor, KAERI is currently developing Advanced SFR design concepts that can better meet the Generation IV technology
goals. This also includes developing, Advanced SFR technologies necessary for its commercialization and basic key technologies,
aiming at the conceptual design of an Advanced SFR by 2011. KAERI is making R&D efforts to develop advanced design
concepts including a passive decay heat removal system and a supercritical CO2 Brayton cycle energy conversion system, as well
as developing design methodologies, computational tools, and sodium technology. The long-term Advanced SFR development
plan will be carried out toward the construction of an Advanced SFR demonstration plant by 2028.
목차
등록된 정보가 없습니다.
참고문헌 (21)
참고문헌 신청
/ 1992 / ASME B&PV Code, Section XI, Division 3, “Rules for In-service Inspection of Nuclear Power Plant Component,” (1992)
Aoki, S. / 1973 / Current Liquid-metal Heat Transfer Research in Japan / Prog. Heat Mass Transfer 7 : 569 ~ 573
Cheng, S. K. / 1986 / Hydrodynamic models and Correlations for Bare Rod and Wire-wrapped Hexagonal Rod Bundles - Bundle Friction Factors, Subchannel Friction Factors and Mix
D. Hahn / 2007 / KALIMER-600 Conceptual Design Report
D. Mohr / 1987 / Loss-of-Primary-Flow-without-Scram Tests: Pretest Predictions and Preliminary Results / N.E.D. 101 : 45 ~ 56
Aoki, S. / 1973 / Current Liquid-metal Heat Transfer Research in Japan / Prog. Heat Mass Transfer 7 : 569 ~ 573
Cheng, S. K. / 1986 / Hydrodynamic models and Correlations for Bare Rod and Wire-wrapped Hexagonal Rod Bundles - Bundle Friction Factors, Subchannel Friction Factors and Mix
D. Hahn / 2007 / KALIMER-600 Conceptual Design Report
D. Mohr / 1987 / Loss-of-Primary-Flow-without-Scram Tests: Pretest Predictions and Preliminary Results / N.E.D. 101 : 45 ~ 56
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