• Title/Summary/Keyword: consequence models

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Development Direction of Fire Consequence Analysis Programs for Hazardous Materials (위험물 취급설비 화재 사고결과 영향평가 프로그램 개발 방향)

  • 유재환;김용수;이영순;이경봉;이성우;박달재
    • Fire Science and Engineering
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    • v.13 no.4
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    • pp.1-6
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    • 1999
  • In this paper, We have analyzed the application characteristics of the three different consequence programs(SuperChems Pro., PHAST Pro., and SAFER Trace) for the models (pool fire, jet fire & flare, fireball, flash fire) based on the four possible accident scenarios. And we have proposed a development direction of fire consequence analysis models using the related theories and the results analysis of consequence programs.

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Development of an Accident Consequence Assessment Code for Evaluating Site Suitability of Light- and Heavy-water Reactors Based on the Korean Technical Standards

  • Hwang, Won Tae;Jeong, Hae Sun;Jeong, Hyo Joon;Kil, A Reum;Kim, Eun Han;Han, Moon Hee
    • Journal of Radiation Protection and Research
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    • v.41 no.4
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    • pp.368-372
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    • 2016
  • Background: Methodologies for a series of radiological consequence assessments show a distinctive difference according to the design principles of the original nuclear suppliers and their technical standards to be imposed. This is due to the uncertainties of the accidental source term, radionuclide behavior in the environment, and subsequent radiological dose. Both types of PWR and PHWR are operated in Korea. However, technical standards for evaluating atmospheric dispersion have been enacted based on the U.S. NRC's positions regardless of the reactor types. For this reason, it might cause a controversy between the licensor and licensee of a nuclear power plant. Materials and Methods: It was modelled under the framework of the NRC Regulatory Guide 1.145 for light-water reactors, reflecting the features of heavy-water reactors as specified in the Canadian National Standard and the modelling features in MACCS2, such as atmospheric diffusion coefficient, ground deposition, surface roughness, radioactive plume depletion, and exposure from ground deposition. Results and Discussion: An integrated accident consequence assessment code, ACCESS (Accident Consequence Assessment Code for Evaluating Site Suitability), was developed by taking into account the unique regulatory positions for reactor types under the framework of the current Korean technical standards. Field tracer experiments and hand calculations have been carried out for validation and verification of the models. Conclusion: The modelling approaches of ACCESS and its features are introduced, and its applicative results for a hypothetical accidental scenario are comprehensively discussed. In an applicative study, the predicted results by the light-water reactor assessment model were higher than those by other models in terms of total doses.

Fragility-based rapid earthquake loss assessment of precast RC buildings in the Marmara region

  • Ali Yesilyurt;Oguzhan Cetindemir;Seyhan O. Akcan;Abdullah C. Zulfikar
    • Structural Engineering and Mechanics
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    • v.88 no.1
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    • pp.13-23
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    • 2023
  • Seismic risk assessment studies are one of the most crucial instruments for mitigating casualties and economic losses. This work utilizes fragility curves to evaluate the seismic risk of single-story precast buildings, which are generally favored in Marmara's organized industrial zones. First, the precast building stock in the region has been categorized into nine sub-classes. Then, seven locations in the Marmara region with a high concentration of industrial activities are considered. Probabilistic seismic hazard assessments were conducted for both the soil-dependent and soil-independent scenarios. Subsequently, damage analysis was performed based on the structural capacity and mean fragility curves. Considering four different consequence models, 630 sub-class-specific loss curves for buildings were obtained. In the current study, it has been determined that the consequence model has a significant impact on the loss curves, hence, average loss curves were computed for each case investigated. In light of the acquired results, it was found that the loss ratio values obtained at different locations within the same region show significant variation. In addition, it was observed that the structural damage states change from serviceable to repairable or repairable to unrepairable. Within the scope of the study, 126 average loss functions were presented that could be easily used by non-experts in earthquake engineering, regardless of structural analysis. These functions, which offer loss ratios for varying hazard levels, are valuable outputs that allow preliminary risk assessment in the region and yield sensible outcomes for insurance activities.

Genetically Optimized Rule-based Fuzzy Polynomial Neural Networks (진화론적 최적 규칙베이스 퍼지다항식 뉴럴네트워크)

  • Park Byoung-Jun;Kim Hyun-Ki;Oh Sung-Kwun
    • Journal of Institute of Control, Robotics and Systems
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    • v.11 no.2
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    • pp.127-136
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    • 2005
  • In this paper, a new architecture and comprehensive design methodology of genetically optimized Rule-based Fuzzy Polynomial Neural Networks(gRFPNN) are introduced and a series of numeric experiments are carried out. The architecture of the resulting gRFPNN results from asynergistic usage of the hybrid system generated by combining rule-based Fuzzy Neural Networks(FNN) with polynomial neural networks (PNN). FNN contributes to the formation of the premise part of the overall rule-based structure of the gRFPNN. The consequence part of the gRFPNN is designed using PNNs. At the premise part of the gRFPNN, FNN exploits fuzzy set based approach designed by using space partitioning in terms of individual variables and comes in two fuzzy inference forms: simplified and linear. As the consequence part of the gRFPNN, the development of the genetically optimized PNN dwells on two general optimization mechanism: the structural optimization is realized via GAs whereas in case of the parametric optimization we proceed with a standard least square method-based learning. To evaluate the performance of the gRFPNN, the models are experimented with the use of several representative numerical examples. A comparative analysis shows that the proposed gRFPNN are models with higher accuracy as well as more superb predictive capability than other intelligent models presented previously.

Shadow and Highlight Invariant Color Models

  • Lee, Ja-Yong;Kang, Hoon
    • Proceedings of the IEEK Conference
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    • 2005.11a
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    • pp.557-560
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    • 2005
  • The color of objects varies with changes in illuminant color and viewing conditions. As a consequence, color boundaries are influenced by a large variety of imaging variables such as shadows, highlights, illumination, and material changes. Therefore, invariant color models are useful for a large number of applications such as object recognitions, detections, and segmentations. In this paper, we propose invariant color models. These color models are independent of the object geometry, object pose, and illumination. From these color models, color invariant edges are derived. To show the validity of the proposed invariant color models, some examples are given.

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Dynamic Replacement Models with Different Technology Levels (다른 기술수준을 갖는 동적장비교체에 관한 연구)

  • 고현우
    • Journal of Korean Society of Industrial and Systems Engineering
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    • v.17 no.32
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    • pp.209-220
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    • 1994
  • In this paper, we study the timing and equipment of replacement. Those affect both available possibility and technological levels of new equipments in the future. These problems are classified according to technological levels and in consequence generated four circumstance. Models are formulated in this research. These are able to make us decision which we replace equipment at the first time. A method is suggested to find the optimal age for replacement at given each circumstance. A solution procedure and numerical example are given.

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Usage Characteristics of Publicly-Available Accidental Release Models (주요 누출사고 예측 모델의 사용 특성 비교)

  • 정수희;윤도영;김영성
    • Journal of Korean Society for Atmospheric Environment
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    • v.15 no.5
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    • pp.687-696
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    • 1999
  • Characteristics of four publicly-available accidental release models, ALOHA, SLAB, HGSYSTEM, and DEGADIS, are compared. These models are world-widely used and recently recommended by the Chemical Dispersion and Consequence Assessment(CDCA) Working Group of the United States as models applicable to generally broad safety-basis documentation applicatons. Four release scenarios are assumed by referring to the usage and storage conditions of toxic substances in the field as well as the USEPA model guideline(1993). Sensitivity of impact radius by varying meteorological conditions is tested in typical and worst-case meteorological conditions. The results show that ALOHA generally gives conservative estimates and the results from HGSYSTEM are sensitive to variations in meteorological conditions.

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Process fault diagnostics using the integrated graph model

  • Yoon, Yeo-Hong;Nam, Dong-Soo;Jeong, Chang-Wook;Yoon, En-Sup
    • 제어로봇시스템학회:학술대회논문집
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    • 1991.10b
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    • pp.1705-1711
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    • 1991
  • On-line fault detection and diagnosis has an increasing interest in a chemical process industry, especially for a process control and automation. The chemical process needs an intelligent operation-aided workstation which can do such tasks as process monitoring, fault detection, fault diagnosis and action guidance in semiautomatic mode. These tasks can increase the performance of a process operation and give merits in economics, safety and reliability. Aiming these tasks, series of researches have been done in our lab. Main results from these researches are building appropriate knowledge representation models and a diagnosis mechanism for fault detection and diagnosis in a chemical process. The knowledge representation schemes developed in our previous research, the symptom tree model and the fault-consequence digraph, showed the effectiveness and the usefulness in a real-time application, of the process diagnosis, especially in large and complex plants. However in our previous approach, the diagnosis speed is its demerit in spite of its merits of high resolution, mainly due to using two knowledge models complementarily. In our current study, new knowledge representation scheme is developed which integrates the previous two knowledge models, the symptom tree and the fault-consequence digraph, into one. This new model is constructed using a material balance, energy balance, momentum balance and equipment constraints. Controller related constraints are included in this new model, which possesses merits of the two previous models. This new integrated model will be tested and verified by the real-time application in a BTX process or a crude unit process. The reliability and flexibility will be greatly enhanced compared to the previous model in spite of the low diagnosis speed. Nexpert Object for the expert system shell and SUN4 workstation for the hardware platform are used. TCP/IP for a communication protocol and interfacing to a dynamic simulator, SPEEDUP, for a dynamic data generation are being studied.

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Model-theoretic Conceptions of Logical Consequences and Logical Constants (모형론적 논리적 귀결과 논리상항)

  • Park, Jun-Yong
    • Korean Journal of Logic
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    • v.17 no.1
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    • pp.71-109
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    • 2014
  • Gila Sher believes that Tarskian definition of logical consequence is a conceptually and extensionally adequate explanation. She has tried to show this on the basis of Mostowskian conceptions of generalized quantifiers as being invariant under isomorphic structures and her own conceptions of models. In this paper I try to show that her attempt to justify the Tarskian definition is only partially successful. I admit that her conceptions of the logical as being invariant under isomorphic structures are enough to show the logical formality of logical consequence relations. But I think that since her conceptions of meanings of terms are quite inadequate for dealing with the problem of empty predicates, she fails to distinguish logically necessary truths from other kinds of truths.

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Multi-unit Level 3 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site

  • Kim, Sung-yeop;Jung, Yong Hun;Han, Sang Hoon;Han, Seok-Jung;Lim, Ho-Gon
    • Nuclear Engineering and Technology
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    • v.50 no.8
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    • pp.1246-1254
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    • 2018
  • The importance of performing Level 3 probabilistic safety assessments (PSA) along with a general interest in assessing multi-unit risk has been sharply increasing after the Fukushima Daiichi nuclear power plant (NPP) accident. However, relatively few studies on multi-unit Level 3 PSA have been performed to date, reflecting limited scenarios of multi-unit accidents with higher priority. The major difficulty to carry out a multi-unit Level 3 PSA lies in the exponentially increasing number of multi-unit accident combinations, as different source terms can be released from each NPP unit; indeed, building consequence models for the astronomical number of accident scenarios is simply impractical. In this study, a new approach has been developed that employs the look-up table method to cover every multi-unit accident scenario. Consequence results for each scenario can be found on the table, established with a practical amount of effort, and can be matched to the frequency of the scenario. Preliminary application to a six-unit NPP site was carried out, where it was found that the difference between full-coverage and cut-off cases could be considerably high and therefore influence the total risk. Additional studies should be performed to fine tune the details and overcome the limitations of the approach.