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Yeon, Jei-Won;Jung, Sang-Hyuk
- Nuclear Engineering and Technology
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- v.49 no.8
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- pp.1689-1695
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- 2017
As a part of evaluating the volatility of iodide ions subjected to gamma irradiation, $I_2$ evaporation experiments were performed with $I_2$ and $I^-$ mixed solutions in the temperature range $26-80^{\circ}C$ in an open, well-ventilated space. The evaporation of $I_2$ was observed to follow primarily first order kinetics, depending on the $I_2$ concentration. The evaporation rate constant increased rapidly with increase in temperature. The presence of $I^-$ slightly reduced the evaporation rate of $I_2$ by forming relatively stable $I_3^-$. The effect of $Cl^-$ at <1.0 wt% on $I_2$ evaporation was insignificant. The evaporation rate constants of $I_2$ were $1.3{\times}10^{-3}min^{-1}\;cm^{-2}$, $2.4{\times}10^{-2}min^{-1}\;cm^{-2}$, and $8.6{\times}10^{-2}min^{-1}\;cm^{-2}$, at $26^{\circ}C$, $50^{\circ}C$, and $80^{\circ}C$, respectively.
https://doi.org/10.1016/j.net.2017.07.018 인용 PDF KSCI

김장열;권기춘
- Proceedings of the Korean Nuclear Society Conference
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- 1995.05a
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- pp.1041-1046
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- 1995
본 논문에서는 원전 I&C Function System Equipment (FSE)의 분류기준을 제시하기 위하여 IEEE 730.1, IEEE 828, IEEE 1012 및 IEC 1226의 관련 표준들을 비교 분석하여 I&C FSE를 근간으로 계측제어 소프트웨어를 원전 I&C 계통의 기능에 따라 Type I, Type II, Type III 및 Type IV로 분류할 수 있는 분류기준, 분류절차 및 예를 제시하였다. 또한, 본 논문의 분류기준을 토대로 하여 최근 이슈가 되고 있는 상용 소프트웨어 (Commercial Off The Shelf Software)의 원전 사용 승인기준을 제시하였다.
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Suh, Yong-Suk;Park, Jae-Hong;Park, Heui-Youn;Son, Ki-Sung;Lee, Ki-Hyun;Kim, Hyeon-Soo
- Proceedings of the Korean Nuclear Society Conference
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- 2005.05a
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- pp.1263-1264
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- 2005
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UPADHYAYA, BELLE R.;LISH, MATTHEW R.;HINES, J. WESLEY;TARVER, RYAN A.
- Nuclear Engineering and Technology
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- v.47 no.2
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- pp.148-156
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- 2015
Several vendors have recently been actively pursuing the development of integral pressurized water reactors (iPWRs) that range in power levels from small to large reactors. Integral reactors have the features of minimum vessel penetrations, passive heat removal after reactor shutdown, and modular construction that allow fast plant integration and a secure fuel cycle. The features of an integral reactor limit the options for placing control and safety system instruments. The development of instrumentation and control (I&C) strategies for a large 1,000 MWe iPWR is described. Reactor system modeling-which includes reactor core dynamics, primary heat exchanger, and the steam flashing drum-is an important part of I&C development and validation, and thereby consolidates the overall implementation for a large iPWR. The results of simulation models, control development, and instrumentation features illustrate the systematic approach that is applicable to integral light water reactors.
https://doi.org/10.1016/j.net.2015.01.001 인용 KSCI

Kang Hyun Gook;Jang Seung-Cheol;Lim Ho-Gon
- Nuclear Engineering and Technology
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- v.36 no.2
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- pp.184-195
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- 2004
The multi-tasking feature of digital I&C equipment could increase risk concentration because the I&C equipment affects the actuation of the safety functions in several ways. Anticipated Transient without Scram (ATWS) is a typical case of safety function failure in nuclear power plants. In a conventional analysis, mechanical failures are treated as the main contributors of the ATWS. This paper quantitatively presents the probability of the ATWS based on a fault tree analysis of a Korea Standard Nuclear Power Plant is also presented. An analysis of the digital equipment in the digital plant protection system. The results show that the digital system severely affects the ATWS frequency. We also present the results of a sensitivity study, which show the effects of the important factors, and discuss the dependency between human operator failure and digital equipment failure.
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