Search | Korea Science

Park, J. H.;Kim, H. P.;Kim, C. S.;Lee, S.
- Proceedings of the Korean Society of Precision Engineering Conference
- /
- 2001.04a
- /
- pp.570-573
- /
- 2001
Safety is very important to operate nuclear power plant. To have the safety, nuclear power plant should be run without trouble. This paper presents the application of a failure diagnosis approach based on discrete event system theory to the Main Feedwater System for Safe Integral Reactor.
PDF

Ilyas, Muhammad;Aydogan, Fatih
- Nuclear Engineering and Technology
- /
- v.49 no.8
- /
- pp.1669-1679
- /
- 2017
Background: Steam generator (SG) is one of the significant components in the nuclear steam supply system. A variety of SGs have been designed and used in nuclear reactor systems. Every SG has advantages and disadvantages. A brief account of some of the existing SG designs is presented in this study. A high surface to volume ratio of a SG is required in small modular reactors to occupy the least space. In this paper, performance improvement for SGs of integral small modular reactor is proposed. Aims/Methods: For this purpose, cross-grooved microfins have been incorporated on the inner surface of the helical tube to enhance heat transfer. The primary objective of this work is to investigate thermal-hydraulic behavior of the proposed improvements through modeling in RELAP5-3D. Results and Conclusions: The results are compared with helical-coiled SGs being used in IRIS (International Reactor Innovative and Secure). The results show that the tube length reduces up to 11.56% keeping thermal and hydraulic conditions fixed. In the case of fixed size, the steam outlet temperature increases from 590.1 K to 597.0 K and the capability of power transfer from primary to secondary also increases. However, these advantages are associated with some extra pressure drop, which has to be compensated.
https://doi.org/10.1016/j.net.2017.08.011 인용 PDF KSCI

박천태;이준;김영인;윤주현;지성균
- Journal of the Korea Academia-Industrial cooperation Society
- /
- v.5 no.4
- /
- pp.350-353
- /
- 2004
The integral reactor is tripped by the boron injection to the reactor when the CEA(Control element assembly) is not available due to its malfunction. In general, the borated water is made by dissolving the boron powder in the water and is stored in a tank. and then injected. But, this method is disadvantageous from the view point of construction cost, operation and maintenance because it has many components and is complicated. In this study, the boron powder direct vessel injection method is adopted to improve the system. Injecting the boron powder directly to the vessel and decreasing of number of components, the system configuration, operation and maintenance is simplified and the construction cost is reduced.
PDF

Bae, Hwang;Kim, Dong Eok;Ryu, Sung-Uk;Yi, Sung-Jae;Park, Hyun-Sik
- Nuclear Engineering and Technology
- /
- v.49 no.5
- /
- pp.968-978
- /
- 2017
Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal-hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery.
https://doi.org/10.1016/j.net.2017.04.006 인용 PDF KSCI