http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
TROI 실험결과를 활용한 원자력발전소 중대사고시 노외 증기폭발 하중평가
박익규(Ik-Kyu Park),김종환(Jong-Hwan Kim),민병태(Beong-Tae Min) 대한기계학회 2009 大韓機械學會論文集B Vol.33 No.8
The TEXAS-V code tuned for TROI-13 was used for analyzing the parametric findings in TROI experiments. The calculations on the melt composition are relatively similar to the TROI experimental results. The water depth effect in TEXAS-V code seems to be consistent with TROI experiments in some degree. The water area effect of TEXAS-V calculations seems not to be harmonious to that in TROI experiments. This seems to indicate that TEXAS-V as 1-dimensional code or as the numerical steam explosion has a limitation on estimating area effect. Thus, TEXAS-V tuned for TROI-13 seems to have an ability to estimate the parametric effect of TROI experiments. The evaluated TEXAS-V was used for estimating the ex-vessel steam explosion load. The calculated explosion pressure and load were about 40 ㎫ and 75 ㎪.sec, which are not much threatening level for containment integrity.
Ik Kyu Park(박익규),Kun Ho Chun(전건호) 한국전산유체공학회 2013 한국전산유체공학회지 Vol.18 No.2
The standard drag force and virtual mass force, which exert to the primary flow direction, are generally considered in two-phase analysis computational codes. In this paper, the lift force, wall lubrication force, and turbulent dispersion force including turbulence models, which are essential for a computational multi-fluid dynamics model and play an important role in motion perpendicular to the primary flow direction, were introduced and verified with conceptual problems.
TROI 실험결과를 활용한 TEXAS-V 코드 검증 및 원자로 노외증기폭발 하중평가
박익규(Ik-Kyu Park),김종환(Jong-Hwan Kim),민병태(Beong-Tae Min),홍성호(Seong-Ho Hong),김희동(Hee-Dong Kim),홍성완(Seong-Wan Hong) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
The TEXAS-V code tuned for TROI-13 was used for analyzing the parametric findings in TROI experiments. The calculations on the melt composition are relatively similar to the TROI experimental results. The water depth effect in TEXAS-V code seems to be consistent with TROI experiments in some degree. The water area effect of TEXAS-V calculations seems not to be harmonious to that in TROI experiments. This seems to indicate that TEXAS-V as 1-dimensional code or as the numerical steam explosion has a limitation on estimating area effect. Thus, TEXAS-V tuned for TROI-13 seems to have an ability to estimate the parametric effect of TROI experiments. The evaluated TEXAS-V was used for estimating the ex-vessel steam explosion load. The calculated explosion pressure and load were about 40 ㎫ and 75 ㎪.sec, which are not much threatening level for containment integrity, but are arguable value for the integrity.
혼합 단계에서의 용용물 입자 크기 분포를 검증 인자로 한 증기폭발 계산
박익규(Ik-Kyu Park),김종환(Jong-Hwan Kim),홍성완(Seong-Wan Hong),민병태(Beong-Tae Min),송진호(Jin-Ho Song),김희동(Hee-Dong Kim) 대한기계학회 2005 대한기계학회 춘추학술대회 Vol.2005 No.11
The reactor steam explosion calculations generally were done by the conventional approach, in which the code verification parameter was a pressure. That conventional approach seemed not to give the consistent result. The explosion pressure by new breakup model is quite different from the explosion pressure by old breakup model even though those two models were tuned for L-14 pressure. The primary reason is that the verification by the pressure could distort the mixture condition. The explosion pressure generally is believed to be the function of mixture conditions such as the fuel particle size distribution and the void fraction, but tuning code to fit mixing pressure data could not guarantee the another mixture condition. The new approach to use the particle size distribution as the comparison parameter was suggested.
원자로 기기 열수력 해석 코드에서 붕소 수송 방정식의 구현
박익규(Ik Kyu Park),이승욱(Seung Wook Lee),윤한영(Han Young Yoon) 한국전산유체공학회 2013 한국전산유체공학회지 Vol.18 No.4
The boron transport model has been implemented into the CUPID code to simulate the boron transport phenomena of the PWR. The boron concentration conservation was confirmed through a simulation of a conceptual boron transport problem in which water with a constant inlet boron concentration injected into an inlet of the 2-dimensional vertical flow tube. The step wise boron transport problem showed that the numerical diffusion of the boron concentration can be reduced by the second order convection scheme. In order to assess the adaptability of the developed boron transport model to the realistic situation, the ROCOM test was simulated by using the CUPID implemented with the boron transportation.
박익규(Ik-Kyu Park),김종환(Jong-Hwan Kim),민병태(Beong-Tae Min),홍성완(Seong-Wan Hong) 대한기계학회 2010 大韓機械學會論文集B Vol.34 No.12
고화 입자 크기의 관점에서 TROI 용융물-냉각수 반응 실험의 결과에 대한 물질 효과를 분석하였다. 고화 입자 크기를 분석하면 용융물-냉각수 반응에서 초기 조건, 혼합, 폭발을 유기적으로 해석할 수 있다. 증기 폭발이 발생한 경우와 폭발이 발생하지 않는 경우의 고화 입자 크기를 분석한 결과 증기 폭발이 발생한 경우에는 미세 입자가 많고 비교적 큰 입자는 적은 것으로 나타났다. 또한, 혼합 과정에 대한 정보를 보존할 수 있는 증기 폭발이 발생하지 않은 용융물-냉각수 반응을 이용하여 용융물 입자 크기에 대한 물질 효과를 분석하였다. 증기 폭발이 잘 발생하는 용융물은 증기 폭발에 참여할 수 있는 큰 입자를 많이 포함하고 있었고, 증기 폭발이 잘 발생하지 않는 용융물은 증기폭발보다는 냉각되기 쉬운 작은 입자 혹은 미세 입자를 많이 포함하고 있었다. The effect of materials on fuel coolant interactions (FCIs) was analyzed on the basis of a solidified particle size response for TROI experiments. The solidified particle size response can provide an understanding of the relationship among the initial condition, the mixing, and an explosion. Through a comparison of the size distributions of the solidified particles in the case of explosive and non-explosive FCIs, it is revealed that an explosive FCI results in the production of a large amount of fine particles and a small amount of large particles. The material effect of the size of solidified particles was analyzed using non-explosive FCIs without losing the information on the mixing. This analysis indicates that an explosive melt includes large particles that participate in the steam explosion, whereas a nonexplosive melt includes smaller particles and finer particles.
원자로 기기 열수력 해석 코드에서 붕소 수송 방정식의 구현
박익규(Ik Kyu Park),이승욱(Seung Wook Lee),윤한영(Han Young Yoon) 한국전산유체공학회 2013 한국전산유체공학회지 Vol.18 No.4
The boron transport model has been implemented into the CUPID code to simulate the boron transport phenomena of the PWR. The boron concentration conservation was confirmed through a simulation of a conceptual boron transport problem in which water with a constant inlet boron concentration injected into an inlet of the 2-dimensional vertical flow tube. The step wise boron transport problem showed that the numerical diffusion of the boron concentration can be reduced by the second order convection scheme. In order to assess the adaptability of the developed boron transport model to the realistic situation, the ROCOM test was simulated by using the CUPID implemented with the boron transportation.
CUPID코드를 활용한 2×2 봉다발 부수로 내부 단상 및 2상 난류유동 해석
이종혁,박익규,이재룡,김정우,Lee, Jong Hyuk,Park, Ik Kyu,Lee, Jae Ryong,Kim, Jungwoo 한국전산유체공학회 2017 한국전산유체공학회지 Vol.22 No.4
It is important to understand the flow characteristic in a subchannel of nuclear rod bundle in the design process of a nuclear reactor considering the safety margin. In this study, the CUPID code was used to simulate the flow phenomena in the $2{\times}2$ rod bundle. The simulation of $2{\times}2$ rod bundle test under single- and two-phase flow conditions were conducted to validate the turbulence model. The liquid velocities at 0.45 m along the flow path with 0 and 45 degree of azimuthal angle were compared with experimental data. The CUPID results were a good agreement with experimental data, though the ones for 0 degree case has a little discrepancy. For the future work, the turbulent flow will be investigated by applying different turbulence models to improve the prediction of velocity near wall.