• Nuclear Engineering and Technology
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• 제44권7호
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• pp.745-754
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• 2012

The correlations between Large Early Release Frequency (LERF) and Early Fatality need to be investigated for risk-informed application and regulation. In Regulatory Guide (RG) -1.174, while there are decision-making criteria using the measures of Core Damage Frequency (CDF) and LERF, there are no specific criteria on LERF. Since there are both huge uncertainties and large costs needed in off-site consequence calculation, a LERF assessment methodology needs to be developed, and its correlation factor needs to be identified, for risk-informed decision-making. A new method for estimating off-site consequence has been presented and performed for assessing health effects caused by radioisotopes released from severe accidents of nuclear power plants in this study. The MACCS2 code is used for validating the source term quantitatively regarding health effects, depending on the release characteristics of radioisotopes during severe accidents. This study developed a method for identifying correlations between LERF and Early Fatality and validates the results of the model using the MACCS2 code. The results of this study may contribute to defining LERF and finding a measure for risk-informed regulations and risk-informed decision-making.

• 한국화재소방학회논문지
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• 제17권1호
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• pp.40-45
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• 2003

본 논문에서는 현재 세계적으로 사용되고 있는 화재 PSA 방법론을 살펴보고 화재방호를 목적으로 위험도 정보를 이용할 시 요구되는 방법론의 개선 사항을 파악하였다. 화재 PSA의 결과 및 이를 통한 통찰(insight)은 의사 결정을 하는데 완전한 기술적인 근거라 하기보다는 위험도 정보를 활용한 의사 결정 과정의 일부로서 사용될 수 있으며, 화재 PSA 결과의 적용 분야와 적용 수준은 PSA에서 사용된 모델의 정확성과 타당성에 좌우된다고 할 수 있다. 따라서 화재 PSA의 유용성은 많은 분야의 연구와 개발을 통해 현재 기술 수준 증진에 따라 확대될 것이며, 그에 따라 더 일관성 있는 결과를 낳게 될 것으로 판단한다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 추계학술발표회요약집
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• pp.173-173
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• 1998

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 추계학술발표회요약집
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• pp.183.2-183
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• 2001

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4601-4619
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• 2022

The classical Probabilistic Safety Analysis (PSA) does not include any time dependence explicitly. However, the success criteria (SC) could evolve during the cycle for some initiating events. In that sense, there is a type of sequence in which this time-dependency is quite important, the family of Anticipated Transient without Scram (ATWS) sequences in Pressurized Water Reactors. Therefore, a new risk-informed approach is proposed in this paper, which makes it possible to obtain the time-dependent SC evolution of the safety functions affected by the Moderator Temperature Coefficient (MTC) value. Then, the evolution of the ATWS conditional core damage probability (CCDP) could be obtained using a PSA model. To quantify the CCDP, the average values of the time-dependent failure probabilities must be computed. Finally, the comparison between the CCDP obtained through the application of the classical PSA approach and the new one makes it possible to quantify the impact of time-dependence on the SC of the headers that this new risk-informed ATWS approach can provide.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.195-195
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• 2002

• Journal of Radiation Protection and Research
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• 제30권2호
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• pp.91-97
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• 2005

베이지안 기법은 객관적 자료 이외에 주관적 지식도 평가에 반영하는 특성으로 인해 최근 PRA에서 널리 사용되고 있다. 본 연구에서는 비파괴검사 장비 분실에 대한 방사선 위험도를 평가하기 위해 베이지안 기법을 활용하였다. U.S. NRC에서 제시한 선원분실 피폭 시나리오를 국내 실정에 맞게 재구성하였고 안전인자의 사고발생 확률에 국한하여 적용하였다. 사고발생 확률수정의 경우 Jeffreys사전분포를 사용한 결과가 모호사전분포를 사용한 결과보다 5 % 베이즈 하한치가 더 낮아서 방사선 사고와 같은 낮은 사고발생 확률을 가지는 시스템에 대한 위험도 평가에 적합하다. 위험도의 결과를 보면 일반인의 연간 예상되는 평균선량은 베이지안 기법이 고전적인 기법에 의거한 평가보다 높은 선량을 나타내는데 이는 수정된 안전인자 확률의 평균이 고전적 확률 참보다 높게 평가된 것에 기인한다. 국내의 경우 방사선 위험도 평가를 위한 자료구축이 미비한 바 베이지안 기법은 위험도 평가에 유용한 대안으로 활용할 수 있으며 이러한 연구는 위험도 정보-기반 규제에 기여할 것이다.

• Nuclear Engineering and Technology
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• 제47권3호
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• pp.362-379
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• 2015

In this study, Nuclear Power Plant (NPP) construction schedule delay risk assessment methodology is developed and the construction delay risk is assessed for turnkey international NPP projects. Three levels of delay factors were selected through literature review and discussions with nuclear industry experts. A questionnaire survey was conducted on the basis of an analytic hierarchy process (AHP) and Relative Importance Index (RII) methods and the schedule delay risk is assessed qualitatively and quantitatively by severity and frequency of occurrence of delay factors. This study assigns four main delay factors to the first level: main contractor, utility, regulatory authority, and financial and country factor. The second and the third levels are designed with 12 sub-factors and 32 sub-sub-factors, respectively. This study finds the top five most important sub-sub-factors, which are as follows: policy changes, political instability and public intervention; uncompromising regulatory criteria and licensing documents conflicting with existing regulations; robust design document review procedures; redesign due to errors in design and design changes; and worldwide shortage of qualified and experienced nuclear specific equipment manufacturers. The proposed combined AHP-RII methodology is capable of assessing delay risk effectively and efficiently. Decision makers can apply risk informed decision making to avoid unexpected construction delays of NPPs.

• Nuclear Engineering and Technology
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• 제41권10호
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• pp.1243-1254
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• 2009

The paper discusses the methodology and the use of probabilistic seismic hazard analysis (PSHA) for nuclear power plants from a European perspective. The increasing importance of risk-informed approaches in the nuclear oversight process observed in many countries has contributed to increasing attention to PSHA methods. Nevertheless significant differences with respect to the methodology of PSHA are observed in Europe. The paper gives an overview on actual projects and discusses the differences in the PSHA-methodology applied in different European countries. These differences are largely related to different approaches used for the treatment of uncertainties and to the use of experts. The development of a probabilistic scenario-based approach is identified as a meaningful alternative to the development of uniform hazard spectra or uniform confidence spectra.

• 한국안전학회지
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• 제33권5호
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• pp.157-163
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• 2018

This paper describes design improvement to a research rector for safety enhancement using Probabilistic Safety Assessment (PSA). This PSA under reactor design was undertaken to assess the level of safety for the design of a research reactor and to evaluate whether it is probabilistically safe to operate and reliable to use. The scope of the PSA reported here is a Level 1 PSA, which addresses the risks associated with the core damage. The technical objectives of this study were to identify accident sequences leading to core damage and to derive design improvement from the dominant accident sequences through the sensitivity analysis. The AIMS-PSA and FTREX were used for the this PSA of the research reactor. The criterion for inclusion was all sequences with a point estimate frequency greater than a truncation value of 1.0E-14/yr. The final result indicates a point estimate of 6.79E-05/yr for the overall Core Damage Frequency (CDF) attributable to internal initiating events for the research reactor under design. Based on the dominant accident sequences from the PSA, the seven kinds of sensitivity analysis were performed and some design improvement items were derived. When the five methods to improve the safety were all applied to the reactor design and emergency operating procedure, its risk was reduced to about 1.21E-06/yr from 6.79E-05/yr. The contribution of LOCA and LOEP with high CDF were significantly reduced by the sensitivity analysis. The safety of the research reactor was well improved and the risk was reduced than before adapting the design improvement gotten from the sensitivity analysis. The present study indicated that the research reactor has the well-balanced safety in regard to each initiating event contribution to CDF. The PSA methodology is very effective to improve reactor safety in a conceptual design phase and especially, Risk-informed design(RID) is very nice way to find the deficiencies of research reactor under design and to improve the reactor safety by solving them.