• Proceedings of the Korea Technology Innovation Society Conference
• /
• 2003.11a
• /
• pp.359-368
• /
• 2003

In the early stage of 21th century, international nuclear society was on the active look out for new direction, and had a common recognition on the necessity of innovative reactor system. To achieve this purpose effectively, several international projects have been initiated for development of new nuclear energy systems that secure stable energy supply and have improved public acceptance, safety, and cost-effectiveness. In this study, status of international projects on future innovative nuclear energy systems and technology goals of future nuclear energy systems were surveyed, and the technological features of Generation IV nuclear energy system were described.

• Journal of Technology Innovation
• /
• v.24 no.4
• /
• pp.221-248
• /
• 2016

In this study, we conducted an in-depth literature review of the innovation characteristics of nuclear technology. We understood that the main issue may be a transition of fourth generation nuclear energy technology. We also analyzed a present status of Korean policy on nuclear energy technology and identified some implications for a successful settlement of the fourth generation nuclear energy technology. This study could provide some policy implications for maintaining the sustainable competitiveness of the fourth generation nuclear energy technology in Korea. According to our study, the factors that influence on a transition of nuclear energy technology are a policy-induced market for technical application and demonstration, stable and long-term resource allocation, constant interaction among stakeholders of innovation, accumulation of skill and know-how for an entire system. In addition, we conducted a case analysis on policy for Korean fourth generation nuclear energy technology. According to this case study, it would be necessary for Korea to pursue systematic training of human resources, active response to a social acceptance and reaction, establishment of specific plan for technical demonstration, long-term policy suggestion, and active promotion of constant interaction between stakeholders.

• Proceedings of the KIEE Conference
• /
• 2007.10a
• /
• pp.305-306
• /
• 2007

본 논문은 차세대 원전 신고리 #3, 4호기 NSSS(Nuclear Steam Supply System) 제어계통의 검증시스템을 개발하기 위한 설계개념에 관한 것이다. 차세대 원전 신고리 #3, 4호기는 KHNP(Korea Hydro & Nuclear Power Co., Ltd.)가 개발한 APR1400(Advanced Power Reactor 1400 [MWe])을 적용하는 최초의 원자력 발전소이다. APR1400은 3세대 원자력발전소로 인정받고 있으며, APR1400 원자력발전소의 안전한 운영을 위하여 I&C(Instrumentation and Control)시스템이 디지털 표준 플랫폼으로 설계되었다[2]. 특히, 차세대 원전 신고리 #3, 4호기의 비안전계통(제어 감시 및 경보계통)은 WEC (Westinghouse Electric Company)의 DCS(Distributed Control System) 상용 단일 플랫폼으로 구성될 예정이다. 우리는 신고리 #3, 4호기의 제어계통 중에서 NSSS(Nuclear Steam Supply System) 제어계통의 검증시스템을 개발하기 위하여 Stimulated Simulator의 방법론을 적용하여 "Simulator"라는 설계 개념을 정립하였다. 현재 원자력발전소 NSSS 제어계통의 DCS Stimulator 개발을 위하여 차세대 원전 신고리 #3, 4호기에 시설될 WEC의 DCS와 Simulation 서버 그리고 I/O 설비를 구축 중에 있으며, 원자력발전소 현장 기기 모델링 소프트웨어와 I/O 설비간의 인터페이스를 위한 동신 소프트웨어도 개발하고 있다.

• Nuclear industry
• /
• v.24 no.9 s.259
• /
• pp.31-38
• /
• 2004

• Nuclear industry
• /
• v.24 no.9 s.259
• /
• pp.22-30
• /
• 2004

• Nuclear industry
• /
• v.22 no.3 s.229
• /
• pp.2-14
• /
• 2002

• Journal of the KSME
• /
• v.50 no.3
• /
• pp.28-31
• /
• 2010

이 글에서는 제4세대(Generation-IV) 원자로시스템의 자원활용 측면에서 핵연료 주기와 관련하여 새롭게 부각되고 있는 소듐냉각고속로(SFR: Sodium-cooled Fast Reactor)의 개발 목적 및 설계 특성을 기술하고 원자로 구조관점에서 가압경수로(PWR)와 비교 설명한다.

• Nuclear industry
• /
• v.29 no.7
• /
• pp.33-36
• /
• 2009

• Nuclear industry
• /
• v.24 no.9 s.259
• /
• pp.47-51
• /
• 2004

• Nuclear industry
• /
• v.24 no.9 s.259
• /
• pp.15-21
• /
• 2004