• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2221-2229
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• 2020

After the Fukushima Daiichi nuclear power plant (NPP) accident, level 3 probabilistic safety assessment (PSA) has emerged as an important task in order to assess the risk level of the multi-unit NPPs in a single nuclear site. Accurate calculation of the radionuclide concentrations and exposure doses to the public is required if a nuclear site has multi-unit NPPs and large number of people live near NPPs. So, there has been a great need to develop a new method or procedure for the fast and accurate offsite consequence calculation for the multi-unit NPP accident analysis. Since the multi-unit level 3 PSA is being currently performed assuming that all the NPPs are located at the same position such as a center of mass (COM) or base NPP position, radionuclide concentrations or exposure doses near NPPs can be drastically distorted depending on the locations, multi-unit NPP alignment, and the wind direction. In order to overcome this disadvantage of the COM method, the idea of a new multiple location (ML) method was proposed and implemented into a new tool MURCC (multi-unit radiological consequence calculator). Furthermore, the MURCC code was further improved for the multi-unit level 3 PSA that has the arbitrary number of multi-unit NPPs. The objectives of this study are to (1) qualitatively and quantitatively compare COM and ML methods, and (2) demonstrate the strength and efficiency of the ML method. The strength of the ML method was demonstrated by the applications to the multi-unit long-term station blackout (LTSBO) accidents at the four-unit Vogtle NPPs. Thus, it is strongly recommended that this ML method be employed for the offsite consequence analysis of the multi-unit NPP accidents.

• 한국안전학회지
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• 제33권6호
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• pp.144-156
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• 2018

Level 3 Probabilistic Safety Assessment (PSA) is performed for the risk assessment that calculates radioactive material dispersion to the environment. This risk assessment is performed with a tool of MELCOR Accident Consequence Code System (MACCS2 or WinMACCS). For the off-site consequence analysis of multi-unit nuclear power plant (NPP) accident, the single location (Center Of Mass, COM) method has been usually adopted with the assumption that all the NPPs in the nuclear site are located at the same COM point. It was well known that this COM calculation can lead to underestimated or overestimated radionuclide concentration. In order to overcome this underestimation or overestimation of radionuclide concentrations in the COM method, Multiple Location (ML) method was developed in this study. The radionuclide concentrations for the individual NPPs are separately calculated, and they are summed at every location in the nuclear site by the post-processing of radionuclide concentrations that is based on two-dimensional Gaussian Plume equations. In order to demonstrate the efficiency of the ML method, radionuclide concentrations were calculated for the six-unit NPP site, radionuclide concentrations of the ML method were compared with those by COM method. This comparison was performed for conditions of constant weather, yearly weather in Korea, and four seasons, and the results were discussed. This new ML method (1) improves accuracy of radionuclide concentrations when multi-unit NPP accident occurs, (2) calculates realistic atmospheric dispersion of radionuclides under various weather conditions, and finally (3) supports off-site emergency plan optimization. It is recommended that this new method be applied to the risk assessment of multi-unit NPP accident. This new method drastically improves the accuracy of radionuclide concentrations at the locations adjacent to or very close to NPPs. This ML method has a great strength over the COM method when people live near nuclear site, since it provides accurate radionuclide concentrations or radiation doses.

• 한국안전학회지
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• 제27권5호
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• pp.224-228
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• 2012

According to the results of Probabilistic Safety Assessment(PSA) for a Nuclear Power Plant(NPP), an Emergency Power Supply(EPS) system has been considered as one of the most important safety system. Especially, the interests in the reliability of the EPS system have been increased after the severe accidents of Fukushima Daiichi. Firstly, we performed the risk assessment and the importance analysis of the EPS system based on the PSA models of the reference plant, which is the Korean standard NPP type. Considering a portable Diesel Generator(DG) system as the reliability reinforcement of the EPS system, we modified the PSA models and performed the risk impact assessment and the importance analysis. Although the reliability of the potable DG could be about 20% of the reliability of the alternative AC DG, we identified that Core Damage Frequency(CDF) was decreased by at least 4.6%. In addition, the risk impacts due to the unavailability of the EPS system on CDF were decreased.

• Nuclear Engineering and Technology
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• 제34권4호
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• pp.331-343
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• 2002

We performed an importance analysis of In-Service Testing (157) components for Ulchin Unit 3 using the integrated evaluation method for categorizing component safety significance developed in this study. The developed method is basically aimed at having a PSA expert perform an importance analysis using PSA and its related information. The importance analysis using the developed method is initiated by ranking the component importance using quantitative PSA information. The importance analysis of the IST components not modeled in the PSA is performed through the engineering judgment, based on the expertise of PSA, and the quantitative and qualitative information for the 157 components. The PSA scope for importance analysis includes not only Level 1 and 2 internal PSA but also Level 1 external and shutdown/low power operation PSA. The importance analysis results of valves show that 167 (26.55%) of the 629 IST valves are HSSCs and 462 (73.45%) are LSSCs. Those of pumps also show that 28 (70%)of the 40157 pumps are HSSCs and 12 (30%) are LSSCs.

• 한국지진공학회논문집
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• 제15권1호
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• pp.57-63
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• 2011

본 연구에서는 중저준위 방사성 폐기물 처분장의 지진위험도 평가를 위한 평가용 입력지반운동을 도출하였다. 방사성 폐기물 처분장 부지를 대상으로 한 지진재해도 평가를 수행하여 재해도 곡선을 도출하였으며 도출된 재해도 곡선을 바탕으로 등재해도 스펙트럼을 산정하였다. 등재해도 스펙트럼에 부합하는 30개의 인공지진파를 생성하여 해당 부지의 지반을 대상으로 한 부지응답해석을 수행하였다. 대상부지에 대한 부지응답해석을 통하여 지표면과 처분동굴의 상단과 하단부에서의 입력지진운동을 구하였고 각각의 평균값을 구하여 방사성 폐기물 처분장의 리스크 평가를 위한 평가용 응답스펙트럼을 제시하였다.

• 한국토양비료학회지
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• 제44권1호
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• pp.38-47
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• 2011

This study focused on health risk assessment via multi-routes of As exposure to establish a target cleanup level (TCL) in abandoned mines. Soil, ground water, and rice samples were collected near ten abandoned mines in November 2009. The As contaminations measured in all samples were used for determining the probabilistic health risk by Monte-Carlo simulation techniques. The human exposure to As compound was attributed to ground water ingestion. Cancer risk probability (R) via ground water and rice intake exceeded the acceptable risk range of $10^{-6}{\sim}10^{-4}$ in all selected mines. In particular, the MB mine showed the higher R value than other mines. The non-carcinogenic effects, estimated by comparing the average As exposure with corresponding reference dose were determined by hazard quotient (HQ) values, which were less than 1.0 via ground water and rice intake in SD, NS, and MB mines. This implied that the non-carcinogenic toxic effects, due to this exposure pathway had a greater possibility to occur than those in other mines. Besides, hazard index (HI) values, representing overall toxic effects by summed the HQ values were also greater than 1.0 in SD, NS, JA, and IA mines. This revealed that non-carcinogenic toxic effects were generally occurred. The As contaminants in all selected mines exceeded the TCL values for target cancer risk ($10^{-6}$) through ground water ingestion and rice intake. However, the As level in soil was greater than TCL value for target cancer risk via inadvertent soil ingestion pathway, except for KK mine. In TCL values for target hazard quotient (THQ), the As contaminants in soil did not exceed such TCL value. On the contrary, the As levels in ground water and polished rice in SD, NS, IA, and MB mines were also beyond the TCL values via ground water and rice intake. This study concluded that the health risks through ground water and rice intake were greater than those though soil inadvertent ingestion and dermal contact. In addition, it suggests that the abandoned mines to exceed the risk-based TCL values are carefully necessary to monitor for soil remediation.

• 한국안전학회지
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• 제15권2호
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• pp.126-135
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• 2000

Probabilistic Safety Assessment (PSA) is an engineering analysis method to identify possible contributors to the risk from a nuclear power plant and now it has become a standard tool in safety evaluation of nuclear power plants. PSA consists of three phases named as Level 1, 2 and 3. Level 2 PSA, mainly focused in this paper, uses a step-wise approach. At first, plant damage states (PDSs) are defined from the Level 1 PSA results and they are quantified. Containment event tree (CET) is then constructed considering the physico-chemical phenomena in the containment. The quantification of CET can be assisted by a decomposition event tree (DET). Finally, source terms are quantitatively characterized by the containment failure mode. As the main benefit of PSA is to provide insights into plant design, performance and environmental impacts, including the identification of the dominant risk contributors and the comparison of options for reducing risk, this technique is expected to be applied to the industrial safety area.

• Journal of Radiation Protection and Research
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• 제16권1호
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• pp.53-72
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• 1991

An integrated model is developed in this paper for the performance assessment of high level radioactive waste repository. This integrated model consists of two simple mathematical models. One is a multiple-barrier failure model of the repository system based on constant failure rates which provides source terms to biosphere. The other is a biosphere model which has multiple pathways for radionuclides to reach to human. For the parametric uncertainty and sensitivity analysis for the risk assessment of high level radioactive waste repository, Latin hypercube sampling and rank correlation techniques are applied to this model. The former is cost-effective for large computer programs because it gives smaller error in estimating output distribution even with smaller number of runs compared to crude Monte Carlo technique. The latter is good for generating dependence structure among samples of input parameters. It is also used to find out the most sensitive, or important, parameter groups among given input parameters. The methodology of the mathematical modelling with statistical analysis will provide useful insights to the decision-making of radioactive waste repository selection and future researches related to uncertain and sensitive input parameters.

• 한국환경농학회지
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• 제30권3호
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• pp.316-322
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• 2011

국내 호소 수역 50지점에서 검출빈도가 비교적 높은 4종의 농약성분에 대해 성수기와 비성수기를 구분하여 오염도를 조사하였고, 위해지수방법과 확률론적인 방법을 적용하여 조류, 물벼룩, 어류, 양서류 등의 수생 종들에 대한 생태위해성 평가를 수행하였다. 조류 종에 대해서는 중간 위해성 수준으로, 그 외 다른 수생 종들의 위해성은 낮은 위해성 기준에 비해 훨씬 낮게 산정되어 위해성이 없는 것으로 평가되었다. 조류 종에 대한 위해성은 주로 제초제인 oxadiazon 성분에 기인하였고, 어류 및 양서류에서도 높은 위해 기여도를 보여주었다. $HC_5$값을 적용한 생태위해지수 또한 oxadiazon 성분에서만 중간 위해성 수준이었고, 이 성분이 수생 종에 위해 영향을 주는 주 기여요인으로 조사되었다. 각 농약성분의 농도가 $HC_5$값에 비해 낮은 수준으로 검출되었고, 혼합된 형태의 농약성분에 대한 결합된 생태위해확률 또한 허용기준인 5% 이하로서 생태위해성이 없는 것으로 평가되었다. 결론적으로, 농업용수를 공급하는 전국 호소 수역의 관리를 위해서는 주기적인 생태위해성평가가 필요하며, 급성독성과 노출량을 비교하는 위해지수와 확률론적 기법은 기초 위해성평가이며, 우리나라 고유 생물 종을 이용한 위해성평가, 만성독성, 환경 중 거동, 환경 요인 등을 모두 고려한 보다 높은 단계의 위해성평가 기법 연구가 반드시 필요할 것으로 사료된다.

• 한국터널지하공간학회 논문집
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• 제10권1호
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• pp.1-15
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• 2008

터널과 같은 지하구조물의 경우에는 지반의 다양한 변동성과 불확실성으로 인하여 터널 시공단계에서의 위험이 계속적으로 종가하고 있으므로, 터널 설계단계에서 터널 안정성 및 환경성에 영향을 주는 위험요소에 대한 위험도 평가 및 관리가 매우 중요하다. 본 연구에서는 터널굴착으로 인한 안정성에 대한 위험도 분석을 지반자체의 지보능력, 지반침하에 의한 인접구조물 손상, 막장내 지하수 유입량, 지진영향 등의 요소로 구분하여 평가하였다. 또한 환경성에 대한 위험도 분석을 발파로 인한 소음 진동, 운영중 열차운행으로 인한 소음 진동, 지하수위 저하로 인한 환경영향 등으로 평가하였다. 이와 같은 위험요소들에 대하여 위험도를 정량적으로 평가하고 터널 전구간에 걸친 위험도의 분포특성을 파악하였다. 또한 다양한 확률론적 기법과 통계자료를 사용하여 각각의 위험도에 대한 비용(cost)을 분석하므로서 위험도가 터널공사에 미치는 영향을 평가하였다. 그리고 본 위험도 평가기법을 터널설계단계에서 적용하므로서 기존의 방법을 보완할 수 있는 보다 합리적인 위험도 평가방법으로서의 유용성을 검토하였다.