• 제목/요약/키워드: Deterministic Risk Assessment

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국내 도로 노면 퇴적입자 내 PAHs의 인체 위해성 평가 (Human Health Risk Assessment of Polycyclic Aromatic Hydrocarbons (PAHs) from Road Dust Sediments in Korea)

  • 이가인;김홍경;지승민;장용철
    • 환경영향평가
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    • 제29권4호
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    • pp.286-297
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    • 2020
  • 본 연구에서는 국내 4개 도시(6개 지점)로부터 도로 노면 퇴적입자 내 PAHs의 농도 및 분포특성을 비교, 분석하고 오염 수준에 대한 초과 발암 위해도를 산정하여 인체 위해성 평가를 수행하였다. 지역별 오염농도를 바탕으로 흡입, 섭취, 피부 노출에 대한 노출경로를 설정하여 결정론적 위해성평가를 수행한 결과, 울산 지역의 경우 위해도 발암 기준 1×10-6을 상회하는 결과가 나타났다. 또한 발암위해도가 있다고 판단되는 해당 지역에 대한 확률론적 위해성평가 결과, 확률적 평균값이 단일값을 활용한 결정론적 위해도 산정에서 도출되었던 발암위해도와 중앙값에 근접한 수준을 나타내었다. 민감도 분석 결과, 노출시간에 따른 기여도가 가장 크게 나타났다. 향후 기준치를 초과하는 발암 위해도를 나타내는 지역에 대한 위해도 관리는 물론 상세한 모니터링을 통한 추가 위해성 평가가 이루어져야 할 것으로 판단되며, 지역적 특성을 반영한 노출계수의 산정을 통해 인체 위해도 평가 결과 신뢰도를 높여야 할 것으로 사료된다.

방사능위해성평가 프로그램 RADCONS의 개발 및 적용 (Development and Application of Radiological Risk Assessment Program RADCONS)

  • 정효준;박미선;황원태;김은한;한문희
    • 환경영향평가
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    • 제22권1호
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    • pp.89-97
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    • 2013
  • RADCONS Ver. 1.0 (RADiological CONSequence Assessment Program) was developed for radiological risk assessment in this study. A Gaussian plume model was used to analyze the fate and transport of radionuclides released into the air in case of accidents. Both single meterological data and time series meterological data can be used in RADCONS. To assess the radiological risk of the early phase after an accident, ED (Effective Dose) estimated by both deterministic and probabilistic approaches are presented. These EDs by deterministic and probabilistic will be helpful to efficient decision making for decision makers. External doses from deposited materials by time are presented for quantifying the effects of mid and late phases of an accident. A radiological risk assessment was conducted using RADCONS for an accident scenario of 1 Ci of Cs-137. The maximum of ED for radii of 1,000 meters from the accident point was 8.51E-4 mSv. After Monte-Carlo simulation, considering the uncertainty of the breathing rate and dispersion parameters, the average ED was 8.49E-4, and the 95 percentile was 1.10E-3. A data base of the dose coefficients and a sampling module of the meteorological data will be modified to improve the user's convenience in the next version.

지진위험도평가 방법을 이용한 내진성능관리 의사결정 (Decision Making of Seismic Performance Management Using Seismic Risk Assessment)

  • 김동주;최지혜;김병화
    • 한국지진공학회논문집
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    • 제23권6호
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    • pp.329-339
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    • 2019
  • The strategy for the management of earthquakes is shifting from post recovery to prevention; therefore, seismic performance management requires quantitative predictions of damage and the establishment of strategies for initial responses to earthquakes. Currently, seismic performance evaluation for seismic management in Korea consists of two stages: preliminary evaluation and detailed evaluation. Also, the priority of seismic performance management is determined in accordance with the preliminary evaluation. As a deterministic method, preliminary evaluation quantifies the physical condition and socio-economic importance of a facility by various predetermined indices, and the priority is decided by the relative value of the indices; however, with the deterministic method it is difficult to consider any uncertainty related to the return-year, epicenter, and propagation of seismic energy. Also this method cannot support tasks such as quantitative socio-economic damage and the provision of data for initial responses to earthquakes. Moreover, indirect damage is often greater than direct damage; therefore, a method to quantify damage is needed to enhance accuracy. In this paper, a Seismic Risk Assessment is used to quantify the cost of damage of road facilities in Pohang city and to support decision making.

케이슨 방파제의 확률론적 지진재해도 평가 (Probabilistic Seismic Hazard Analysis of Caisson-Type Breakwaters)

  • 김상훈;김두기
    • 한국해양공학회지
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    • 제19권1호
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    • pp.26-32
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    • 2005
  • Recent earthquakes, measuring over a magnitude of 5.0, on the eastern coast of Korea, have aroused interest in earthquake analyses and the seismic design of caisson-type breakwaters. Most earthquake analysis methods, such as equivalent static analysis, response spectrum analysis, nonlinear analysis, and capacity analysis, are deterministic and have been used for seismic design and performance evaluation of coastal structures. However, deterministic methods are difficult for reflecting on one of the most important characteristics of earthquakes, i.e. the uncertainty of earthquakes. This paper presents results of probabilistic seismic hazard assessment(PSHA) of an actual caisson-type breakwater, considering uncertainties of earthquake occurrences and soil properties. First, the seismic vulnerability of a structure and the seismic hazard of the site are evaluated, using earthquake sets and a seismic hazard map; then, the seismic risk of the structure is assessed.

RISK-INFORMED REGULATION: HANDLING UNCERTAINTY FOR A RATIONAL MANAGEMENT OF SAFETY

  • Zio, Enrico
    • Nuclear Engineering and Technology
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    • 제40권5호
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    • pp.327-348
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    • 2008
  • A risk-informed regulatory approach implies that risk insights be used as supplement of deterministic information for safety decision-making purposes. In this view, the use of risk assessment techniques is expected to lead to improved safety and a more rational allocation of the limited resources available. On the other hand, it is recognized that uncertainties affect both the deterministic safety analyses and the risk assessments. In order for the risk-informed decision making process to be effective, the adequate representation and treatment of such uncertainties is mandatory. In this paper, the risk-informed regulatory framework is considered under the focus of the uncertainty issue. Traditionally, probability theory has provided the language and mathematics for the representation and treatment of uncertainty. More recently, other mathematical structures have been introduced. In particular, the Dempster-Shafer theory of evidence is here illustrated as a generalized framework encompassing probability theory and possibility theory. The special case of probability theory is only addressed as term of comparison, given that it is a well known subject. On the other hand, the special case of possibility theory is amply illustrated. An example of the combination of probability and possibility for treating the uncertainty in the parameters of an event tree is illustrated.

확률적 접근방법에 의한 지반의 액상화 가능성 평가 (Evaluation of Liquefaction Potential for Soil Using Probabilistic Approaches)

  • 이진학;권오순;박우선
    • 대한토목학회논문집
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    • 제26권5C호
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    • pp.313-322
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    • 2006
  • 지반 액상화는 대표적인 지진 피해의 한 형태로 이 연구에서는 이러한 지반 액상화 가능성 평가를 위한 확률적 접근 방법을 제시하였다. 일정한 사용기간 동안의 지진에 의한 액상화 발생확률을 구하기 위하여 액상화 취약도와 지진재해도를 결합하여 액상화 위험도를 산정할 수 있도록 하였다. 현재 국내에서는 결정론적인 방법이 많이 이용되고 있으나, 이러한 방법은 지반 물성치에 포함되어 있는 많은 불확실성을 합리적으로 다루기 어려운 단점이 있다. 두 가지 형태의 확률적 접근 방법을 제시하였는데, 첫번째는 설계지진에 대한 확률적 신뢰도 해석 방법이고, 두번째는 주어진 지반조건에 대하여 일정한 사용기간 동안 액상화가 발생할 수 있는 가능성을 평가한 위험도 해석 방법이다. 기존의 결정론적 방법과 확률적 방법에 의하여 매립지반의 액상화를 평가하였으며, 위험도 해석에 의한 액상화 가능성 평가기법을 지속적으로 적용하고, 설계기준이 제시된다면 보다 합리적이고, 정량적인 지반 액상화 가능성 평가기법이 될 수 있음을 검증하였다.

A New Approach to Selection of Inspection Items using Risk Insight of Probabilistic Safety Assessment for Nuclear Power Plants

  • Park, Younwon;Kim, Hyungjin;Lim, Jihan;Choi, Seongsoo
    • 한국압력기기공학회 논문집
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    • 제14권2호
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    • pp.49-58
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    • 2018
  • The regulatory periodic inspection program (PSI) conducted at every overhaul period is the most important process for confirming the safety of nuclear power plants. The PSI for operating nuclear power plants in Korea mainly consist of component level performance check that had been developed based on deterministic approach putting the same degree of importance to all the inspection items. This inspection methodology is likely to be effective for preoperational inspection. However, once the plant is put into service, the PSI must be focused on whether to minimize the risk of accident using defense-in-depth concept and risk insight. The incorporation of defense-in-depth concept and risk insight into the deterministic based safety inspection has not been well studied so far. In this study, two track approaches are proposed to make sure that core damage be avoided: one is to secure success path and the other to block the failure path in a specific event tree of PSA. The investigation shows how to select safety important components and how to set up inspection group to ensure that core damage would not occur for a given initiating event, which results in strengthening defense-in-depth level 3.

확률론적 평가법과 결정론적 평가법에 의한 내진성능비교분석 (The Comparison of Seismic Capacities Of Two Approaches, Probabilistic Approach and Deterministic Approach)

  • 송정국;황규호;강선구;서용표;이종림
    • 한국지진공학회:학술대회논문집
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    • 한국지진공학회 2003년도 춘계 학술발표회논문집
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    • pp.101-109
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    • 2003
  • In evaluating the individual Plant Examination of Seismic Events, two methodologies, Seismic Probabilistic Risk Assessment(SPRA) and Seismic Margin Assessment(SMA) can be used. SPRA is based on the probubilistic approach and SMA is based on the deterministic approach in evaluating seismic capacities. In this paper, by evaluating the seismic capacities of the same component by these two approaches respectively, the correlation of two methodologies can be shown. In addition, the meaning of HCLPF(High Confidence of Low Probability of Failure) values that are inherent in these two methodologies is recognized by the quantitative comparison analysis.

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Integrated Level 1-Level 2 decommissioning probabilistic risk assessment for boiling water reactors

  • Mercurio, Davide;Andersen, Vincent M.;Wagner, Kenneth C.
    • Nuclear Engineering and Technology
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    • 제50권5호
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    • pp.627-638
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    • 2018
  • This article describes an integrated Level 1-Level 2 probabilistic risk assessment (PRA) methodology to evaluate the radiological risk during postulated accident scenarios initiated during the decommissioning phase of a typical Mark I containment boiling water reactor. The fuel damage scenarios include those initiated while the reactor is permanently shut down, defueled, and the spent fuel is located into the spent fuel storage pool. This article focuses on the integrated Level 1-Level 2 PRA aspects of the analysis, from the beginning of the accident to the radiological release into the environment. The integrated Level 1-Level 2 decommissioning PRA uses event trees and fault trees that assess the accident progression until and after fuel damage. Detailed deterministic severe accident analyses are performed to support the fault tree/event tree development and to provide source term information for the various pieces of the Level 1-Level 2 model. Source terms information is collected from accidents occurring in both the reactor pressure vessel and the spent fuel pool, including simultaneous accidents. The Level 1-Level 2 PRA model evaluates the temporal and physical changes in plant conditions including consideration of major uncertainties. The goal of this article is to provide a methodology framework to perform a decommissioning Probabilistic Risk Assessment (PRA), and an application to a real case study is provided to show the use of the methodology. Results will be derived from the integrated Level 1-Level 2 decommissioning PSA event tree in terms of fuel damage frequency, large release frequency, and large early release frequency, including uncertainties.