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박동환;김명현
- Proceedings of the Korean Nuclear Society Conference
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- 1997.10a
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- pp.158-163
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- 1997
신형 경수로심의 네가지 개념설계안을 제시하였다. 각 설계안은 압력관내에 농축우라늄 핵연료 다발을 CANDU처럼 장전하고 냉각수를 경수로 바꾼 안으로써 본 연구는 각 설계안의 장단점과 타당성을 검토하였다. 가연성 독봉인 IFBA를 사용하여 기존 CANDU 제어 시스템만으로 노심 잉여반응도의 제어가 가능함을 확인하였다.
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Jeong, Dae-Yul;Lim, Hyuk-Soon;Jeong, Dae-Wok;Heo, Gyun-Young
- Proceedings of the KSME Conference
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- 2001.06d
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- pp.343-347
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- 2001
Advanced Pressurized Reactor 1400(APR-1400), which is a standard evolutionary advanced light water reactor(ALWR), has been developed from 1992 as one of long-term Government Project(G-7). The APR-1400 is designed to operate at the rated output of 4000MWt to produce an electric power output of around 1450MWe. The balance of plant (BOP) for the secondary system consists of main steam, feedwater, condensate, turbine generator and auxiliary system. In this paper, we describe the major design features of secondary component, balance of plant configuration, and then the turbine cycle thermal performance evaluation using PEPSE code.
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Lim, Hyuk-Soon;Chung, Dae-Yul;Byun, Sung-Chul;Lee, Kwang-Han
- Proceedings of the KSME Conference
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- 2003.04a
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- pp.49-54
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- 2003
Most of the operating pressurized water reactors (PWRs)has chosen Inconel 600 as steam generator tubing. The long-term operation of steam generators showed that the use of this material induced localized corrosion damages. The current trend is using Inconel 690 as a tube material for the replacement steam generators. Based on the current trend, we have chosen Inconel 690 for the advanced Power Reactor 1400 (APR1400) steam generator tube material. In this paper, we examined the technical consideration in this modification: the effect of chemical composition, thermal conductivity, corrosion resistance and wear characteristics
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