• 제목/요약/키워드: Probabilistic sensitivity

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Concrete bridge deck deterioration model using belief networks

  • Njardardottir, Hrodny;McCabe, Brenda;Thomas, Michael D.A.
    • Computers and Concrete
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    • 제2권6호
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    • pp.439-454
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    • 2005
  • When deterioration of concrete is observed in a structure, it is highly desirable to determine the cause of such deterioration. Only by understanding the cause can an appropriate repair strategy be implemented to address both the cause and the symptom. In colder climates, bridge deck deterioration is often caused by chlorides from de-icing salts, which penetrate the concrete and depassivate the embedded reinforcement, causing corrosion. Bridge decks can also suffer from other deterioration mechanisms, such as alkali-silica reaction, freeze-thaw, and shrinkage. There is a need for a comprehensive and integrative system to help with the inspection and evaluation of concrete bridge deck deterioration before decisions are made on the best way to repair it. The purpose of this research was to develop a model to help with the diagnosis of concrete bridge deck deterioration that integrates the symptoms observed during an inspection, various deterioration mechanisms, and the probability of their occurrence given the available data. The model displays the diagnosis result as the probability that one of four deterioration mechanisms, namely shrinkage, corrosion of reinforcement, freeze-thaw and alkali-silica reaction, is at fault. Sensitivity analysis was performed to determine which probabilities in the model require refinement. Two case studies are included in this investigation.

노심손상빈도 평가를 위한 APR+ PAFS의 안전 해석 (Safety Analysis of APR+ PAFS for CDF Evaluation)

  • 강상희;문호림;박영섭
    • 한국안전학회지
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    • 제28권3호
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    • pp.123-128
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    • 2013
  • The Advanced Power Reactor Plus(APR+), which is a GEN III+ reactor based on the APR1400, is being developed in Korea. In order to enhance the safety of the APR+, a passive auxiliary feedwater system(PAFS) has been adopted in the APR+. The PAFS replaces the conventional active auxiliary feedwater system(AFWS) by introducing a natural driving force mechanism while maintaining the system function of cooling the primary side and removing the decay heat. As the PAFS completely replaces the conventional AFWS, it is required to verify the cooling capacity of PAFS for the core damage frequency(CDF) evaluation. For this reason, this paper discusses the cooling performance of the PAFS during transient accidents. The test case and scenarios were picked from the result of the sensitivity analysis in APR+ Probabilistic Safety Assessment(PSA). The analysis was performed by the best estimate thermal-hydraulic code, RELAP5/.MOD3.3. This study shows that the plant maintains the stable state without the core damages under the given test scenarios. The results of PSA considering this analysis' results shows that the CDF values are decreased. The analysis results can be used for more realistic and accurate performance of a PSA.

Vessel failure sensitivities of an advanced reactor for SBLOCA

  • Jhung, Myung Jo;Oh, Chang-Sik;Choi, Youngin;Kang, Sung-Sik
    • Nuclear Engineering and Technology
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    • 제52권1호
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    • pp.185-191
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    • 2020
  • Plant-specific analyses of an advanced reactor have been performed to assure the structural integrity of the reactor pressure vessel during transient conditions, which are expected to initiate pressurized thermal shock (PTS) events. The vessel failure probabilities from the probabilistic fracture mechanics analyses are combined with the transient frequencies to generate the through-wall cracking frequencies, which are compared to the acceptance criterion. Several sensitivity analyses are performed, focusing on the orientations and sizes of cracks, the copper content, and a flaw distribution model. The results show that the integrity of the reactor vessel is expected to be maintained for long-term operation beyond the design lifetime from the PTS perspective using the design data of the advanced reactor. Moreover, a fluence level exceeding 9×1019 n/㎠ is found to be acceptable, generating a sufficient margin beyond the design lifetime.

Monte Carlo analysis of the induced cracked zone by single-hole rock explosion

  • Shadabfar, Mahdi;Huang, Hongwei;Wang, Yuan;Wu, Chenglong
    • Geomechanics and Engineering
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    • 제21권3호
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    • pp.289-300
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    • 2020
  • Estimating the damage induced by an explosion around a blast hole has always been a challenging issue in geotechnical engineering. It is difficult to determine an exact dimension for damage zone since many parameters are involved in the formation of failures, and there are some uncertainties lying in these parameters. Thus, the present study adopted a probabilistic approach towards this problem. First, a reliability model of the problem was established and the failure probability of induced damage was calculated. Then, the corresponding exceedance risk curve was developed indicating the relation between the failure probability and the cracked zone radius. The obtained risk curve indicated that the failure probability drops dramatically by increasing the cracked zone radius so that the probability of exceedance for any crack length greater than 4.5 m is less than 5%. Moreover, the effect of each parameter involved in the probability of failure, including blast hole radius, explosive density, detonation velocity, and tensile strength of the rock, was evaluated by using a sensitivity analysis. Finally, the impact of the decoupling ratio on the reduction of failures was investigated and the location of its maximum influence was demonstrated around the blast point.

Evaluation of soil spatial variability by micro-structure simulation

  • Fei, Suozhu;Tan, Xiaohui;Wang, Xue;Du, Linfeng;Sun, Zhihao
    • Geomechanics and Engineering
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    • 제17권6호
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    • pp.565-572
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    • 2019
  • Spatial variability is an inherent characteristic of soil, and auto-correlation length (ACL) is a very important parameter in the reliability or probabilistic analyses of geotechnical engineering that consider the spatial variability of soils. Current methods for estimating the ACL need a large amount of laboratory or in-situ experiments, which is a great obstacle to the application of random field theory to geotechnical reliability analysis and design. To estimate the ACL reasonably and efficiently, we propose a micro-structure based numerical simulation method. The quartet structure generation set algorithm is used to generate stochastic numerical micro-structure of soils, and scanning electron microscope test of soil samples combined with digital image processing technique is adopted to obtain parameters needed in the QSGS algorithm. Then, 2-point correlation function is adopted to calculate the ACL based on the generated numerical micro-structure of soils. Results of a case study shows that the ACL can be estimated efficiently using the proposed method. Sensitivity analysis demonstrates that the ACL will become stable with the increase of mesh density and model size. A model size of $300{\times}300$ with a grid size of $1{\times}1$ is suitable for the calculation of the ACL of clayey soils.

Development of a reference framework to assess stylized human intrusion scenarios using GENII Version 2 considering design features of planned near-surface disposal facility in Korea

  • Kwon, Ki Nam;Cheong, Jae Hak
    • Nuclear Engineering and Technology
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    • 제51권6호
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    • pp.1561-1574
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    • 2019
  • A standard form of six stylized human intrusion scenarios for a near-surface disposal facility (e.g. the planned Korean repository, Gyeongju Phase II) is proposed through re-categorization of totally thirty-one past cases reported in public literature. A reference assessment framework for inadvertent human intrusion is newly developed using GENII Version 2 conforming to the ICRP Publication 60 and thereafter. Calculated dose from the assessment framework is verified by comparing with hand calculation results for simplified model equations independently derived. Results from GENII Version 2 and 1.485 show inevitable differences, which is mainly attributed to the difference in the external dose assessment model. If intake dose coefficients in GENII Version 1.485 are modified, the difference can be reduced but still exist to an extent. Through deterministic and probabilistic sensitivity analysis, most affecting four parameters are derived and uncertainties of the parameters are quantified. It is expected that the reference assessment framework together with representative stylized scenarios can be used to do a human intrusion impact assessment for a specific repository using site-specific information. Especially, the past practice of human intrusion impact assessment using GENII Version 1.485 with or without modification may be replaced with the new assessment framework developed in this study.

다수기 PSA 기반 원자력 발전소 이동형 안전 설비 활용성 평가 (Evaluating the Application of Portable Safety Equipment in Nuclear Power Plants using Multi-unit PSA)

  • 윤재영;임호곤;박종우
    • 한국안전학회지
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    • 제38권3호
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    • pp.110-120
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    • 2023
  • Following the Fukushima accident, portable equipment employed as accident mitigating systems have been installed and operated to reduce core damage and large early release frequencies. In addition, the establishment of an accident management strategy has gained importance. This study investigated the current status of portable equipment including the international portable equipment FLEX (diverse and flexible coping strategies), and domestic portable equipment multi-barrier accident coping strategy (MACST). Research on optimal utilization of MACST remains insufficient. As a preliminary study for establishing an optimal strategy, sensitivity studies were conducted to facilitate the priority of use on portable equipment, number of portable equipment, and dependency of operator actions based on a multi-unit probabilistic safety assessment model. The results revealed the conditions that reduced the multi-unit and site conditional core damage probabilities, indicating the optimal strategy of MACST. The results of this study can be used as a reference for establishing an optimal strategy that utilizes domestic safety equipment in the future.

원자력발전소 중대사고시 수소연소로 인한 격납용기 파손에 대한 확률적인 분석 (The Probabilistic Analysis on the Containment Failure by Hydrogen Burning at Severe Accidents in Nuclear Power Plants)

  • 박익규;문주현;박군철
    • Nuclear Engineering and Technology
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    • 제26권3호
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    • pp.411-419
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    • 1994
  • 원자력발전소 중대사고시 예상되는 수소생성과 이에 따른 수소연소로 인한 압력증가로 야기되는 격납용기의 파손화률을 몬테카를로 방법을 통하여 계산하였다. 몬테카를로 계산을 수행하기 위해서는 각각의 입력변수들에 대한 적절한 확률분포함수가 요구되는데, 통계적인 처리를 통하여 구하였다. 고리 2호기에 대한 계산을 수행하였으며, 입력변수들에 대한 민감도 분석도 실시하였다. 고리 2호기에서 수소연소로 인한 격납용기의 파손확률은 60% 이하로 계산되었으며, 민감도 분석결과 SFD가 중요한 인자이긴 하지만 다른 인자들도 무시할 수 없는 영향을 미치고 있음이 밝혀졌다.

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확률론적 지진해일 재해도 평가(PTHA)를 위한 단층 파라미터에 대한 지진해일의 민감도 분석 (Study of tsunami sensitivity analysis to fault parameters for probabilistic tsunami hazard assessment)

  • 정현기;강준호;조용식
    • 한국수자원학회:학술대회논문집
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    • 한국수자원학회 2022년도 학술발표회
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    • pp.274-274
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    • 2022
  • 확률론적 지진해일 재해도 평가(PTHA)는 최근 지진해일에 대한 연구에서는 관심을 많이 받고 있는 주제로 여러 국가에서 연구가 진행되고 있다. 단층매개변수의 민감도 분석은 일본(Goda et al., 2014), 미국(Sepúlveda and Liu, 2016), 뉴질랜드(D. Burbridge et al., 2015) 등에서 연구가 활발하게 이루어졌으며 현재도 활발한 연구가 진행되고 있다. 민감도 분석은 PTHA를 진행하기 위한 선행 과정으로 파향선 추적을 통한 대상지 설정 및 연구 대상 단층을 선정한 후 로직트리를 만들기 위해 각 단층 매개변수의 범위와 단위 폭을 제시한다. 해당 연구는 세 가지 단층 매개변수에 대한 지진해일 초기파와 파고에 대한 민감도 분석을 실행했다. 주향각은 초기파와 지진해일고에 대해서 임의의 변동을 보이지만 변동 폭은 다른 두 매개변수들과 비교하여 가장 크다. 경사각과 슬립각은 단층의 수직 움직임을 변화시키며 이를 통해 초기파의 변동을 예측할 수 있다. 초기파의 변동과 모양을 분석함으로써 수치 계산이 가설과 유사한 결과를 보임을 확인하였다. 경사각과 슬립각에 의한 지진해일고의 변화는 최저 지진해일고가 초기파의 총 에너지와 연관된다는 결론에 이른다. 지진해일 재해도는 해안지역에 도달하는 최종 파고와 관련이 있으므로 각 매개변수의 단위 폭은 지진해일고의 결과를 통해 선정되었다. 민감도 분석은 제시한 주향각, 경사각, 슬립각의 단위 폭을 이용하여 로직트리의 분기 수를 감소시켜 수치 계산 시간을 줄임으로써 PTHA의 효율성을 증대시킨다.

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Stochastic buckling quantification of porous functionally graded cylindrical shells

  • Trinh, Minh-Chien;Kim, Seung-Eock
    • Steel and Composite Structures
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    • 제44권5호
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    • pp.651-676
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    • 2022
  • Most of the experimental, theoretical, and numerical studies on the stability of functionally graded composites are deterministic, while there are full of complex interactions of variables with an inherently probabilistic nature, this paper presents a non-intrusive framework to investigate the stochastic nonlinear buckling behaviors of porous functionally graded cylindrical shells exposed to inevitable source-uncertainties. Euler-Lagrange equations are theoretically derived based on the three variable refined shear deformation theory. Closed-form solutions for the shell buckling loads are achieved by solving the deterministic eigenvalue problems. The analytical results are verified with numerical results obtained from finite element analyses that are conducted in the commercial software ABAQUS. The non-intrusive framework is completed by integrating the Monte Carlo simulation with the verified closed-form solutions. The convergence studies are performed to determine the effective pseudorandom draws of the simulation. The accuracy and efficiency of the framework are verified with statistical results that are obtained from the first and second-order perturbation techniques. Eleven cases of individual and compound uncertainties are investigated. Sensitivity analyses are conducted to figure out the five cases that have profound perturbative effects on the shell buckling loads. Complete probability distributions of the first three critical buckling loads are completely presented for each profound uncertainty case. The effects of the shell thickness, volume fraction index, and stochasticity degree on the shell buckling load under compound uncertainties are studied. There is a high probability that the shell has non-unique buckling modes in stochastic environments, which should be known for reliable analysis and design of engineering structures.