• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.116.1-116.1
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.120.2-120
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2003.10a
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• pp.83.2-83.2
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• 2003

• Journal of Convergence for Information Technology
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• v.11 no.12
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• pp.90-96
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• 2021

In this paper, we designed manufactured and design an integrated interface control unit that has compatibility with brightness control unit, color control unit, and existing control unit. As the implementation method the standard of DVI/HDMI transmission method is applied to the data transmission method, and the Sil 1169 IC is used as the applied IC. Brightness control is programmed to have eight levels of brightness control using the AT89C2051. Also, EPM240T100C5 IC was used for image and dimming data processing. As a result, it is compatible with the control unit using the DVI/HDMI transmission method manufactured by each company and can reproduce clear high quality full HD video according to the surrounding brightness through the full color LED display system.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.181.2-181
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.148.2-148
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• 2002

• Nuclear Engineering and Technology
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• v.26 no.1
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• pp.63-77
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• 1994

The objective of this work is to investigate fluid mixing phenomena related to pressurized thermal shock(PTS) in a pressurized water reactor(PWR) vessel downcomer during transient cooldown with direct vessel injection(DVI) using test models. The test model designs were based on ABB Combustion Engineering(C-E) System 80＋ reactor geometry. A cold leg small break loss-of-coolant accident(LOCA) md a main steam line teak were selected as the potential PTS events for the C-E System 80＋. This work consist of two parts. The first part provides the visualization tests of the fluid mixing between DVI fluid and existing coolant in the downcomer region, and the second part is to compare the results of thermal mixing tests with DVI in the other test model. Row visualization tests with DVI have clarified the physical interaction between DVI fluid and primary coolant during transient cooldown. A significant temperature drop was observed in the downcomer during the tests of a small break LOCA Measured transient temperature profiles agree well with the predictions by the REMIX code for a small break LOCA and with the calculations by the COMMIX-1B code for a steam line break event.

• KOREAN JOURNAL OF CROP SCIENCE
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• v.44 no.2
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• pp.149-153
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• 1999

Prediction of rice developmental stage is necessary for proper crop management and a prerequisite for growth simulation as well. The objectives of the present study were to find out the relationship between the plastochrone index(PI) and the developmental index(DVI) estimated by non-parametric phenology model which simulates the duration from seedling emergence(DVI=0) to heading(DVI=l) by employing daily mean air temperature and daylength as predictor variables, and to confirm the correspondency of developmental indice to panicle developmental stages based on this relationship. Four japonica rice cultivars, Kwanakbyeo, Sangpungbyeo, Dongjinbyeo, and Palgumbyeo which range from very early to very late in maturity, were grown by sowing directly in dry paddy field five times at an interval of two weeks. Data for seedling emergence, leaf appearance, differentiation stage of primary rachis branch and heading were collected. The non-parametric phenology model predicted well the duration from seedling emergence to heading with errors of less than three days in all sowings and cultivars. PI was calculated for every leaf appearance and related to the developmental index estimated for corresponding PI. The stepwise polynomial analysis produced highly significant square-rooted cubic or biquadratic equations depending on cultivars, and highly significant square-rooted biquadratic equation for pooled data across cultivars without any considerable reduction in accuracy compared to that for each cultivar. To confirm the applicability of this equation in predicting the panicle developmental stage, DVI at differentiation stage of primary rachis branch primordium was calculated by substituting PI with 82 corresponding to this stage, and the duration reaching this DVI from seedling emergence was estimated. The estimated duration revealed a good agreement with that observed in all sowings and cultivars. The deviations between the estimated and the observed were not greater than three days, and significant difference in accuracy was not found for predicting this developmental stage between those equations derived for each cultivar and for pooled data across all cultivars tested.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.304-309
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• 1996

차세대원자로(KNGR) 안전주입계통은 원자로용기 하향유로(RVDC)로 직접주입(DVI)되도록 설계되며 이는 4-트레인 안전주입계통의 설계에 있어 고유한 기본구조이다. DIV 채택으로 인해 가압열충격(PTS)과 관련된 인허가 상의 관심사론 조사하고 DVI 주입구 위치에 대한 RVDC에서의 유체거동과 온도분포를 상용전산코드인 FLOW3D를 이용하여 분석하였다. PTS관점에서 가장 최악의 경우인 외부 전원상실을 동반한 영출력 주증기관 파단사고를 해석대상으로 하였으며 사고후 570 ~ 600초 사이의 과도상태를 분석하였다. 본 연구의 결과로 주증기관 파단으로 야기되는 자연순환에 의한 열혼합은 충분히 이루어져 RVDC에서의 온도가 R $T_{PTS}$ 이상임을 확인했고 손상루프측 위의 DVI 주입구의 유동중 일부가 손상루프측 저온관 유동과 상호작용하여 건전루프측 저온관아래로 흐르며 이 영향으로 건전루프측 저온관 아래에서의 온도가 국부적으로 감소함을 확인하였다.다.

• Nuclear Engineering and Technology
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• v.41 no.5
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• pp.691-708
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• 2009

In order to analyze thermal hydraulic phenomena during a DVI (Direct Vessel Injection) line break LOCA (Loss-of-Coolant Accident) in the APR1400 (Advanced Power Reactor 1400 MWe), we performed experimental studies with the SNUF (Seoul National University Facility), a reduced-height and reduce-pressure integral test loop with a scaled down APR1400. We performed experiments dealing with eight test cases under varied tests. As a result of the experiment, the primary system pressure, the coolant temperature, and the occurrence time of the downcomer seal clearing were affected significantly by the thermal power in the core and the SI flow rate. The break area played a dominant role in the vent of the steam. For our analytical investigation, we used the MARS code for simulation of the experiments to validate the calculation capability of the code. The results of the analysis showed good and sufficient agreement with the results of the experiment. However, the analysis revealed a weak capability in predicting the bypass flow of the SI water toward the broken DVI line, and it was insufficient to simulate the streamline contraction in the broken side. We, hence, need to improve the MARS code.