• Title/Summary/Keyword: risk assessment code

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Collapse Probability of a Low-rise Piloti-type Building Considering Domestic Seismic Hazard (국내 지진재해도를 고려한 저층 필로티 건물의 붕괴 확률)

  • Kim, Dae-Hwan;Kim, Taewan;Chu, Yurim
    • Journal of the Earthquake Engineering Society of Korea
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    • v.20 no.7_spc
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    • pp.485-494
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    • 2016
  • The risk-based assessment, also called time-based assessment of structure is usually performed to provide seismic risk evaluation of a target structure for its entire life-cycle, e.g. 50 years. The prediction of collapse probability is the estimator in the risk-based assessment. While the risk-based assessment is the key in the performance-based earthquake engineering, its application is very limited because this evaluation method is very expensive in terms of simulation and computational efforts. So the evaluation database for many archetype structures usually serve as representative of the specific system. However, there is no such an assessment performed for building stocks in Korea. Consequently, the performance objective of current building code, KBC is not clear at least in a quantitative way. This shortcoming gives an unresolved issue to insurance industry, socio-economic impact, seismic safety policy in national and local governments. In this study, we evaluate the comprehensive seismic performance of an low-rise residential buildings with discontinuous structural walls, so called piloti-type structure which is commonly found in low-rise domestic building stocks. The collapse probability is obtained using the risk integral of a conditioned collapse capacity function and regression of current hazard curve. Based on this approach it is expected to provide a robust tool to seismic safety policy as well as seismic risk analysis such as Probable Maximum Loss (PML) commonly used in the insurance industry.

Development of RBI Procedures and Implementation of a Software Based on API Code (II) - Semi-Quantitative Approach (API 기준에 근거한 RBI 절차 개발 및 소프트웨어의 구현 (II) -준정량적 접근법-)

  • Song, Jung-Soo;Shim, Sang-Hoon;Kwon, Jung-Rock;Yoon, Kee-Bong
    • Journal of the Korean Society of Safety
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    • v.17 no.4
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    • pp.110-118
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    • 2002
  • During the last ten years, the need has been increase for reducing maintenance cost for aged equipments are ensuring safety, efficiency and profitability of petrochemical and refinery plants. American Petroleum institute(API) developed a code, API 581 for proposing standard procedures of risk based inspection. Even though the API 581 code covers general RBI procedures, there must be some limitations. In this study, a semi-quantitative assessment algorithm for RBI based on the API 581 code was reconstructed for developing an RBI software. The user-friendly realRBI software is developed with a module for evaluation semi-quantitative risk category using the potential consequence factor and the likelihood factor. Also, inspection planning module for inspection time and inspection method for equipments are included.

A novel risk assessment approach for data center structures

  • Cicek, Kubilay;Sari, Ali
    • Earthquakes and Structures
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    • v.19 no.6
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    • pp.471-484
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    • 2020
  • Previous earthquakes show that, structural safety evaluations should include the evaluation of nonstructural components. Failure of nonstructural components can affect the operational capacity of critical facilities, such as hospitals and fire stations, which can cause an increase in number of deaths. Additionally, failure of nonstructural components may result in economic, architectural, and historical losses of community. Accelerations and random vibrations must be under the predefined limitations in structures with high technological equipment, data centers in this case. Failure of server equipment and anchored server racks are investigated in this study. A probabilistic study is completed for a low-rise rigid sample structure. The structure is investigated in two versions, (i) conventional fixed-based structure and (ii) with a base isolation system. Seismic hazard assessment is completed for the selected site. Monte Carlo simulations are generated with selected parameters. Uncertainties in both structural parameters and mechanical properties of isolation system are included in simulations. Anchorage failure and vibration failures are investigated. Different methods to generate fragility curves are used. The site-specific annual hazard curve is used to generate risk curves for two different structures. A risk matrix is proposed for the design of data centers. Results show that base isolation systems reduce the failure probability significantly in higher floors. It was also understood that, base isolation systems are highly sensitive to earthquake characteristics rather than variability in structural and mechanical properties, in terms of accelerations. Another outcome is that code-provided anchorage failure limitations are more vulnerable than the random vibration failure limitations of server equipment.

Risk Assessment Technique for Gas Fuel Supply System of Combined Cycle Power Plants (I) : Based on API RBI Procedures (복합화력발전의 가스연료 공급계통에 대한 위험도 평가 기법 연구 (I) : API RBI 절차에 기반한 위험도 평가)

  • Song, Jung Soo;Yu, Jong Min;Han, Seung Youn;Choi, Jeong Woo;Yoon, Kee Bong
    • Journal of Energy Engineering
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    • v.27 no.2
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    • pp.1-13
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    • 2018
  • The proportion of natural gas-fueled power generation is expanding due to the change of domestic energy policy pursuing reduction of dust and increasing clean energy consumption. Natural gas fuels used for the combined-cycle power plants and the district-heating power plants are operated at high temperature and high pressure in the fuel supply system. Accidents due to leakage of the gas such as fire and explosion should be prevented by applying risk management techniques. In this study, risk assessment was performed on the natural gas fuel supply system of a combined power plant based on the API RP 581 RBI code. For the application of the API RBI code, lines and segments of the evaluation target system were identified. Operational data and input information were analyzed for the calculations of probability of failure and consequence of failure. The results of the risk assessment were analyzed over time from the initial installation time. In the code-based evaluation, the gas fuel supply system was mainly affected by thinning, external damage, and mechanical fatigue damage mechanisms. As the operating time passes, the risk is expected to increase due to the external damage caused by the CUI(Corrosion Under Insulation).

Development of a RBI Procedure and Implementation of a Software Based on API Code (I) - Qualitative Approach (API기준에 근거한 RBI 절차 개발 및 소프트웨어의 구현 (I) 정성적 접근법)

  • 심상훈;송정수;김지윤;윤기봉
    • Journal of the Korean Society of Safety
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    • v.17 no.3
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    • pp.66-72
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    • 2002
  • During the last ten years, effort has been made for reducing maintenance cost for aged equipments and ensuring safety, efficiency and profitability of petrochemical and refinery plants. Hence, it was required to develop advanced methods which meet this need. RBI(Risk Based Inspection) methodology is one of the most promising technology satisfying the requirements in the field of integrity management. In this study, a qualitative assessment algorithm for RBI based on the API 581 code was reconstructed for developing an RBI software. The user-friendly realRBI software is developed with a module for evaluating qualitative risk category using the potential consequence factor and the likelihood factor.

Multi-unit Level 2 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site

  • Cho, Jaehyun;Han, Sang Hoon;Kim, Dong-San;Lim, Ho-Gon
    • Nuclear Engineering and Technology
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    • v.50 no.8
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    • pp.1234-1245
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    • 2018
  • The risk of multi-unit nuclear power plants (NPPs) at a site has received considerable critical attention recently. However, current probabilistic safety assessment (PSA) procedures and computer code do not support multi-unit PSA because the traditional PSA structure is mostly used for the quantification of single-unit NPP risk. In this study, the main purpose is to develop a multi-unit Level 2 PSA method and apply it to full-power operating six-unit OPR1000. Multi-unit Level 2 PSA method consists of three steps: (1) development of single-unit Level 2 PSA; (2) extracting the mapping data from plant damage state to source term category; and (3) combining multi-unit Level 1 PSA results and mapping fractions. By applying developed multi-unit Level 2 PSA method into six-unit OPR1000, site containment failure probabilities in case of loss of ultimate heat sink, loss of off-site power, tsunami, and seismic event were quantified.

Risk assessment of heavy metals in tuna from Japanese restaurants in the Republic of Korea

  • Seong-Jin Bae;Kyu-Sik Shin;Chulyong Park;Kiook Baek;So-Young Son;Joon Sakong
    • Annals of Occupational and Environmental Medicine
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    • v.35
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    • pp.3.1-3.11
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    • 2023
  • Background: Studies on the risk of mercury (Hg) in Korean fishery products focus primarily on total Hg levels as opposed to methylmercury (MeHg) levels. None of the few studies on MeHg in tuna investigated tuna from Japanese restaurants. Few have evaluated lead (Pb), cadmium (Cd) and arsenic (As) in tuna. Thus, this study aimed to conduct a risk assessment by evaluating heavy metal concentrations in tuna from Japanese restaurants. Methods: Thirty-one tuna samples were collected from Japanese restaurants in the Republic of Korea. They were classified according to region and species. The concentration of heavy metals in the samples was analyzed using the Ministry of Food and Drug Safety Food Code method. The rate of exceedance of maximum residue levels (MRLs) and the risk compared to the provisional tolerable weekly intake (PTWI) set by the Joint Food and Agriculture Organization/World Health Organization Expert Committee on Food Additives (%PTWI) were evaluated for risk assessment. Results: The mean of MeHg, Pb, Cd and As concentrations were 0.56 ± 1.47 mg/kg, 33.95 ± 3.74 ㎍/kg, 14.25 ± 2.19 ㎍/kg and 1.46 ± 1.89 mg/kg, respectively. No sample exceeded the MRLs of Pb and Cd, but 9.7% of the samples exceeded the MRL of MeHg. The %PTWIs of MeHg, Pb, Cd and As were 4.2037, 0.0162, 0.0244 and 1.1627, respectively. The %PTWI of MeHg by age group and sex was highest among men aged 19-29 years (10.6494), followed by men aged 30-49 years (7.2458) and women aged 19-29 years (4.8307). Conclusions: We found that 3 out of 31 samples exceeded the MRL of MeHg. The %PTWI of MeHg showed significant differences based on age and sex, and the value was likely to exceed a safe level depending on individuals' eating behaviors. Therefore, improved risk management for MeHg is required.

Combining in-plane and out-of-plane behaviour of masonry infills in the seismic analysis of RC buildings

  • Manfredi, V.;Masi, A.
    • Earthquakes and Structures
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    • v.6 no.5
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    • pp.515-537
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    • 2014
  • Current seismic codes (e.g. the NTC08 Italian code and the EC8 European code) adopt a performance-based approach for both the design of new buildings and the assessment of existing ones. Different limit states are considered by verifying structural members as well as non structural elements and facilities which have generally been neglected in practice. The key role of non structural elements on building performance has been shown by recent earthquakes (e.g. L'Aquila 2009) where, due to the extensive damage suffered by infills, partitions and ceilings, a lot of private and public buildings became unusable with consequent significant socio-economic effects. Furthermore, the collapse of infill panels, particularly in the case of out-of-plane failure, represented a serious source of risk to life safety. This paper puts forward an infill model capable of accounting for the effects arising from prior in-plane damage on the out-of-plane capacity of infill panels. It permits an assessment of the seismic performance of existing RC buildings with reference to both structural and non structural elements, as well as of their mutual interaction. The model is applied to a building type with RC framed structure designed only to vertical loads and representative of typical Italian buildings. The influence of infill on building performance and the role of the out-of-plane response on structural response are also discussed.

A STUDY ON METHODOLOGY FOR IDENTIFYING CORRELATIONS BETWEEN LERF AND EARLY FATALITY

  • Kang, Kyungmin;Jae, Moosung;Ahn, Kwang-Il
    • Nuclear Engineering and Technology
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    • v.44 no.7
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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.

Safety Assessment on the Incineration Disposal of Regulation Exempt Waste by RESRAD Code (RESRAD 코드를 활용한 규제해제 폐기물 소각처분에 대한 안정성 평가)

  • Kim, Hui-Gyeong;Han, Sang-Wook;Park, Su-Ri;Kim, Byung-Jick
    • Journal of radiological science and technology
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    • v.41 no.1
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    • pp.67-73
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    • 2018
  • In this paper, risk assessment was conducted to verify self - disposal requirements by landfill for exempted incineration ash by using Resrad Ver.6.5 computer code. The result of risk assessment by landfill for the incineration by-product is that individual dose is $6.91{\times}10^{-2}{\mu}Sv\;y-1$ and collective dose is $3.475{\times}10^{-7}man-Sv\;y-1$. It proved that the result meets reference dose of individual dose $10{\mu}Sv\;y-1$ and collective dose 1 man-Sv y-1 for general public. According to the current 'Nuclear Safety Commission Notice [No. 2014-3]', it states that the exempted wastes can be disposed of by incineration, landfill and recycling. However, most of recently documents and papers related to exempted wastes are disposed of by landfill and recyling and it could not confirm the case of exempt by incineration. If the national consensus is derived and treating the waste by using process of incineration is activated, it could be considered to treat low level of radiation wastewater and activated carbon excluded from exempted waste because of nuclide $^3H$ and $^{14}C$.