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SMART연구로의 보수적인 급수관 파단사고 해석방법론 개발
정영종(Y. J. Chung),김수형(S. H. Kim),김희경(H. K Kim),김희철(H. C. Kim),지성균(S. Q. Zee) 대한기계학회 2005 대한기계학회 춘추학술대회 Vol.2005 No.5
Various sizes and types of advanced small and medium sized nuclear reactors are currently nuder development worldwide. The SMART-P, which is an integral pressurized water reactor is one of those advanced types of small sized nuclear reactor. a Feedwater pipe break accident is one of the most important accidents in the safety of the SMART-P plant. Decreased feedwater flow rate to the steam generators causes a decrease in the heat extraction from the reactor coolant system, resulting in a increase of the primary coolant temperature and pressure Performed sensitivity analysis to find parameters affecting seriously in SMART-P's feedwater pipe break accident. According to these sensitivity analysis results, an initial pressurizer pressure, a moderator reactivity coefficient, a power level and a break size are major parameters for the maximum pressure of the reactor coolant system point of view. the pressure in the reactor coolant system and the secondary system for all the cases investigated, remains below 18.7㎫ which is a safety criteria for SMART-P.
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김영인(Y.I. Kim),배영민(Y.M. Bae),정영종(Y.J. Chung),김긍구(K.K. Kim) 한국전산유체공학회 2015 한국전산유체공학회지 Vol.20 No.1
SMART adopts, very unique facility, an FMHA to enhance the thermal and flow mixing capability in abnormal conditions of some steam generators or reactor coolant pumps. The FMHA is important for enhancing thermal mixing of the core inlet flow during a transient and even during accidents, and thus it is essential that the thermal mixing characteristics of flow of the FMHA be understood. Investigations for the mixing characteristics of the FMHA had been performed by using experimental and CFD methods in KAERI. In this study, the temperature distribution at the core inlet region is investigated for several abnormal conditions of steam generators using the commercial code, FLUENT 12. Simulations are carried out with two kinds of FMHA shapes, different mesh resolutions, turbulence models, and steam generator conditions. The CFD results show that the temperature deviation at the core inlet reduces greatly for all turbulence models and steam generator conditions tested here, and the effect of mesh refinement on the temperature distribution at the core inlet is negligible. Even though the uniformity of FMHA outlet hole flow increases the thermal mixing, the temperature deviation at the core inlet is within an acceptable range. We numerically confirmed that the FMHA applied in SMART has an excellent mixing capability and all simulation cases tested here satisfies the design requirement for FMHA thermal mixing capability.
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