• Title/Summary/Keyword: 취.배수구 해수

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Evaluation and Consideration on Environmental Radiation Analysis of Yeong-Gwang Nuclear Power Plant Site Inside&Outside(2000~2009 year) (영광원전 부지 내.외부의 환경방사능 분석에 대한 평가 및 고찰(2000~2009년))

  • Han, Sang-Jun;Lee, Seung-Jin;Lee, Goung-Jin;Lee, Na-Young;Kim, Hee-Gang;Mun, Ji-Yeon
    • Journal of Radiation Protection and Research
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    • v.36 no.2
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    • pp.71-78
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    • 2011
  • Yeong-Gwang N.P.P Private Environment Supervisory Organization analyzed over 3,000 samples including 10 marine and 24 land samples from the year 2,000 to 2009. According to the results of the analysis, artificial nuclides that resulted from the effect of Yeong-Gwang Nuclear Power Plant operations were not detected in most samples. However, from the rain and seawater samples, which were taken from inside the plants such as the intake, the discharge and the observatory, $^3H$ was detected although it was below the regulation level. The $^3H$ concentration detected in the rain taken from the observatory, by the yearly average criterion, was 30.5~40.0 $Bq{\cdot}L^{-1}$, which is around 20 times the $^3H$ concentration detected in the surroundings of the power plants, but it is 0.1% of the regulation level of 40,000 $Bq{\cdot}L^{-1}$. Also, $^3H$ concentration detected in the seawater taken from the intake and the discharge, by the yearly average criterion, was 2.75~17.8$Bq{\cdot}L^{-1}$, which means the concentration detected in the discharge is about 140~280% higher than that detected in the intake except the year 2006. Based on these results, it was determined that, although lower than the regulation level, the $^3H$ in gas and liquid form detected in the rain and seawater sampled from the observatory and the discharge was released into the environment from the power plants. Therefore, regular monitoring and analysis is required on the level of $^3H$ in the observatory and the discharge.

Investigation of Hydraulic Flow Properties around the Mouths of Deep Intake and Discharge Structures at Nuclear Power Plant by Numerical Model (수치모의를 통한 원자력 발전소 심층 취·배수 구조물 유·출입구 주변에서의 수리학적 흐름특성 고찰)

  • Lee, Sang Hwa;Yi, Sung Myeon;Park, Byong Jun;Lee, Han Seung
    • KSCE Journal of Civil and Environmental Engineering Research
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    • v.32 no.2A
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    • pp.123-130
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    • 2012
  • A cooling system is indispensable for the fossil and nuclear power plants which produce electricity by rotating the turbines with hot steam. A cycle of the typical cooling system includes pumping of seawater at the intake pump house, exchange of heat at the condenser, and discharge of hot water to the sea. The cooling type of the nuclear power plants in Korea recently evolves from the conventional surface intake/discharge systems to the submerged intake/discharge systems that minimize effectively an intake temperature rise of the existing plants and that are beneficial to the marine environment by reducing the high temperature region with an intensive dilution due to a high velocity jet and density differential at the mixing zone. It is highly anticipated that the future nuclear power plants in Korea will accommodate the submerged cooling system in credit of supplying the lower temperature water in the summer season. This study investigates the approach flow patterns at the velocity caps and discharge flow patterns from diffusers using the 3-D computational fluid dynamics code of $FLOW-3D^{(R)}$. The approach flow test has been conducted at the velocity caps with and without a cap. The discharge flow from the diffuser was simulated for the single-port diffuser and multi-ports diffuser. The flow characteristics to the velocity cap with a cap demonstrate that fish entrainment can significantly be minimized on account of the low vertical flow component around the cap. The flow pattern around the diffuser is well agreed with the schematic diagram by Jirka and Harleman.

Model Development for the Surface Discharge of Heated Water using Turbulence Model (난류모델을 이용한 표면 온배수 확산모형의 개발)

  • 최흥식;이길성
    • Proceedings of the Korea Water Resources Association Conference
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    • 1989.07a
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    • pp.113-114
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    • 1989
  • 원자력, 화력발전소, 제철소 등의 다양한 임해 공업시설로부터 방출되는 냉각용 온배수는 연안일대 해수의 열균형을 파괴시켜 생태계의 보존 및 환경관리에 좋지 못한 영향을 야기케 된다. 이러한 영향은 해안 또는 만내의 수중온도를 전반적으로 높일뿐 아니라 가동중단시 갑자기 수온을 떨어뜨려 해양생물상에 피해를 줄수도 있다. 또한 온배수에 의하여 온도가 상승된 해수가 취수구를 통하여 재순환되어 냉각기능의 부진을 초래하게되면 발전효율 또는 기계가동율을 저하시키게 된다. 이러한 측면에서 온배수의 확산에 대한 정성, 정량적인 예측은 환경영향평가, 취.배수구 설계조건의 산정 등에 매우 중요한 문제라 하겠다. 본 연구는 정지수역으로 유입하는 3차원 정상류 표면온배수 해석모형의 개발로서 개발된 모형의 수치실험을 통하여 온배수 확산의 물리적 특성을 규명한다. 지배방정식에 나타나는 Reynolds 응력항($)과 온도유동 프럭스항($)의 해석에서 필요한 난류모델은 k-$\varepsilon$ 모형에 난류 평균자승 온도유동($) 및 그 감쇄방정식을 추가한 4-방정식 모델로서 구성하였다. 아울러 3차원 정상류 모형에서 야기되는 타원형 방정식을 포물형 방정식의 형태로 전환하여 효과적으로 해석할 수 있도록 모델의 특성을 정리하였다. 본 모델의 검증을 위하여 Lal 및 Rajaratnam(1977)의 물리적 실험값과 비교해본 결과 온배수 거동의 물리적현상이 잘 일치하였다. 또한 McGuirk 및 Rodi(1979)에 의해 개발된 2-방정식 k-$\varepsilon$ 난류모형의 해석결과에 대하여 비교분석을 실시하였다.

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