• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.202.1-202
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• 1999

• Transactions of the Korean Society of Mechanical Engineers B
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• v.36 no.7
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• pp.767-774
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• 2012

A fluidic device (FD) has been adopted in the safety injection tanks (SITs) of APR1400. A flow control mechanism of the FD was used to vary the flow regime in the vortex chamber corresponding to the SITs water level. The flow regime in the vortex chamber has a different pressure loss from low to high in accordance with the SITs water level. Nitrogen at the top of the SIT could be released owing to inertia of discharge flow when changing from a high flow rate to a low flow rate. This phenomenon is important to design improvement perspective because it can affect the performance of the FD. This paper shows a result of a preliminary numerical study to obtain the transient data related to air release in the flow turn-down period using a two-fluid free-surface model provided from ANSYS CFX 13.0. In conclusion, there is no significant effect on the performance of the FD, though a small quantity of air is released during the flow turn-down period.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.399-404
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• 1996

1000MWt 급 가압경수로의 질량 및 에너지 방출량을 감소시키기 위한 방안으로 울진 3,4호기를 기준으로 안전주입계통의 형태 및 용량을 변화시키면서 원자로냉각재펌프 토출관 및 고온관 파단에 대한 질량 및 에너지 방출량 계산과 격납건물 첨두압력 및 온도의 민감도를 분석하여, 후속호기 설계에 활용하고자 한다. 분석한 여러 경우 중에서, 토출관 파단사고시 안전주입탱크 용량은 변화시키지 않고 고압안전주입펌프 용량을 l75%로 증가시키면서 저압안전주입펌프를 제거하였을 경우가 격납건물 첨두압력 및 온도가 61.98 psia (3.32 kg/$\textrm{cm}^2$A), 288.03 ℉ (142.24$^{\circ}C$)로써 가장 낮게 나타났다. 이러한 결과는 격납건물의 설계여유도를 기존보다 더 확보하므로 안전성이 향상 될 뿐만 아니라. 저압안전주입펌프를 안전주입계통에서 제외함으로써 발전소 운전에도 큰 도움이 될 것이다.

• Journal of Energy Engineering
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• v.26 no.3
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• pp.71-77
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• 2017

In the event of loss of coolant accident (LOCA) and station black out (SBO) in the primary system of a nuclear reactor, the coolant water should be injected to reactor coolant system (RCS) without any intervention of operators or active components. To satisfy the requirements, hybrid safety injection tank (Hybrid SIT) was suggested by Korea Atomic Energy Research Institute (KAERI). The pressure equalizing time of Hybrid SIT is an important parameter to determine the timing of coolant injection. To predict the pressure equalizing time of the Hybrid SIT, a separate effect test facility was constructed and sensitivity tests were conducted in various conditions. The main parameter determining the pressure equalizing time was obtained from separate effect test (SET) results. The wall of condensation on the inner wall of SIT and direct contact condensation on the water surface affected to the pressure equalizing time very much. In this study, the effect of each condensation phenomena on pressure equalizing time was quantitatively analyzed from results of SET and a prediction method of pressure equalizing time was proposed.

• Journal of Energy Engineering
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• v.25 no.4
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• pp.124-132
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• 2016

In order to estimate the effect of flow distributors connected to an upper nozzle of CMT(Core Makeup Tank) on the thermal-hydraulic characteristics in the tank, a simplified 2 inch Small Break Loss of Coolant Accident(SBLOCA) was simulated by skipping the decay power and Passive Residual Heat Removal System(PRHRS) actuation. The CMT is a part of safety injection systems in the SMART (System Integrated Modular Advanced Reactor). Each test was performed with reliable boundary conditions. It means that the pressure distribution is provided with repeatable and reproducible behavior during SBLOCA simulations. The maximum flow rates were achieved at around 350 seconds after the initial opening of the isolation valve installed in CMT. After a short period of decreased flow rate, it attained a steady injection flow rate after about 1,250 seconds. This unstable injection period of the CMT coolant is due to the condensation of steam injected into the upper part of CMT. The steady injection flow rate was about 8.4% higher with B-type distributor than that with A-type distributor. The gravity injection during hot condition tests were in good agreement with that during cold condition tests except for the early stages.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.111-111
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.135-135
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• 2002

• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 2007.11a
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• pp.120-125
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• 2007

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.190-190
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.168-168
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• 2002