• Title/Summary/Keyword: fault trees

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Level 1 probabilistic safety assessment of supercritical-CO2-cooled micro modular reactor in conceptual design phase

  • So, Eunseo;Kim, Man Cheol
    • Nuclear Engineering and Technology
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    • v.53 no.2
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    • pp.498-508
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    • 2021
  • Micro reactors are increasingly being considered for utilization as distributed power sources. Hence, the probabilistic safety assessment (PSA) of a direct supercritical-CO2-cooled fast reactor, called micro modular reactor (MMR), was performed in this study; this reactor was developed using innovative design concepts. It adopted a modular design and passive safety systems to minimize site constraints. As the MMR is in its conceptual design phase, design weaknesses and valuable safety insights could be identified during PSA. Level 1 internal event PSA was carried out involving literature survey, system characterization, identification of initiating events, transient analyses, development of event trees and fault trees, and quantification. The initiating events and scenarios significantly contributing to core damage frequency (CDF) were determined to identify design weaknesses in MMR. The most significant initiating event category contributing to CDF was the transients with the power conversion system initially available category, owing to its relatively high occurrence frequency. Further, an importance analysis revealed that the safety of MMR can be significantly improved by improving the reliability of reactor trip and passive decay heat removal system operation. The findings presented in this paper are expected to contribute toward future applications of PSA for assessing unconventional nuclear reactors in their conceptual design phases.

Evaluation of availability of nuclear power plant dynamic systems using extended dynamic reliability graph with general gates (DRGGG)

  • Lee, Eun Chan;Shin, Seung Ki;Seong, Poong Hyun
    • Nuclear Engineering and Technology
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    • v.51 no.2
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    • pp.444-452
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    • 2019
  • To assess the availability of a nuclear power plant's dynamic systems, it is necessary to consider the impact of dynamic interactions, such as components, software, and operating processes. However, there is currently no simple, easy-to-use tool for assessing the availability of these dynamic systems. The existing method, such as Markov chains, derives an accurate solution but has difficulty in modeling the system. When using conventional fault trees, the reliability of a system with dynamic characteristics cannot be evaluated accurately because the fault trees consider reliability of a specific operating configuration of the system. The dynamic reliability graph with general gates (DRGGG) allows an intuitive modeling similar to the actual system configuration, which can reduce the human errors that can occur during modeling of the target system. However, because the current DRGGG is able to evaluate the dynamic system in terms of only reliability without repair, a new evaluation method that can calculate the availability of the dynamic system with repair is proposed through this study. The proposed method extends the DRGGG by adding the repair condition to the dynamic gates. As a result of comparing the proposed method with Markov chains regarding a simple verification model, it is confirmed that the quantified value converges to the solution.

A Study on the Constructions of Fire Events Probabilistic Safety Assessment Model for Nuclear Power Plants (원자력발전소의 화재사건 확률론적안전성평가 모델 구축에 관한 연구)

  • Kang, Dae Il;Kim, Kilyoo
    • Journal of the Korean Society of Safety
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    • v.31 no.5
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    • pp.187-194
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    • 2016
  • A single fire event within a fire area can cause multiple initiating events considered in internal events probabilistic safety assessment (PSA). For an example, a fire event in turbine building fire area can cause a loss of the main feed-water and loss of off-site power initiating events. This fire initiating event could result in special plant responses beyond the scope of the internal events PSA model. One approach to address a fire initiating event is to develop a specific fire event tree. However, the development of a specific fire event tree is difficult since the number of fire event trees may be several hundreds or more. Thus, internal fire events PSA model has been generally constructed by modifications of the pre-developed internal events PSA model. New accident sequence logics not covered in the internal events PSA model are separately developed to incorporate them into the fire PSA model. Recently, many fire PSA models have fire induced initiating event fault trees not shown in an internal event PSA model. Up to now, there has been no analytical comparative study on the constructions of fire events PSA model using internal events PSA model with and without fault trees of initiating events. In this study, the changing process of internal events PSA model to fire events PSA model is analytically presented and discussed.

A Fast Transmission of Mobile Agents Using Binomial Trees (바이노미얼 트리를 이용한 이동 에이전트의 빠른 전송)

  • Cho, Soo-Hyun;Kim, Young-Hak
    • The KIPS Transactions:PartA
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    • v.9A no.3
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    • pp.341-350
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    • 2002
  • As network environments have been improved and the use of internet has been increased, mobile agent technologies are widely used in the fields of information retrieval, network management, electronic commerce, and parallel/distributed processing. Recently, a lot of researchers have studied the concepts of parallel/distributed processing based on mobile agents. SPMD is the parallel processing method which transmits a program to all the computers participated in parallel environment, and performs a work with different data. Therefore, to transmit fast a program to all the computers is one of important factors to reduce total execution time. In this paper, we consider the parallel environment consisting of mobile agents system, and propose a new method which transmits fast a mobile agent code to all the computers using binomial trees in order to efficiently perform the SPMD parallel processing. The proposed method is compared with another ones through experimental evaluation on the IBM's Aglets, and gets greatly better performance. Also this paper deals with fault tolerances which can be occurred in transmitting a mobile agent using binomial trees.

Sensitivity Analysis According to Fault Parameters for Probabilistic Tsunami Hazard Curves (단층 파라미터에 따른 확률론적 지진해일 재해곡선의 민감도 분석)

  • Jho, Myeong Hwan;Kim, Gun Hyeong;Yoon, Sung Bum
    • Journal of Korean Society of Coastal and Ocean Engineers
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    • v.31 no.6
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    • pp.368-378
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    • 2019
  • Logic trees for probabilistic tsunami hazard assessment include numerous variables to take various uncertainty on earthquake generation into consideration. Results from the hazard assessment vary in different way as more variables are considered in the logic tree. This study is conducted to estimate the effects of various scaling laws and fault parameters on tsunami hazard at the nearshore of Busan. Active fault parameters, such as strike angle, dip angle and asperity, are adjusted in the modelling of tsunami propagation, and the numerical results are used in the sensitivity analysis. The influence of strike angle to tsunami hazard is not as much significant as it is expected, instead, dip angle and asperity show a considerable impact to tsunami hazard assessment. It is shown that the dip angle and the asperity which determine the initial wave form are more important than the strike angle for the assessment of tsunami hazard in the East Sea.

The Study on the Lifetime Estimation using Fault Tree Analysis in Design Process of LNG Compressor (천연가스 압축기 설계 단계에서 FTA를 이용한 수명 예측 연구)

  • Han, Yongshik;Do, Kyu Hyung;Kim, Taehoon;Kim, Myungbae;Choi, Byungil
    • Transactions of the Korean hydrogen and new energy society
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    • v.26 no.2
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    • pp.192-198
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    • 2015
  • Fault Tree Analysis to predict the lifetime in the design process of LNG compressor is considered. Fault Trees for P & ID of the compressor are created. Individual components that comprise the compressor are configured with the basic event. The failure rates in the PDS and OREDA are applied. As results, the system failure rate and the reliability over time are obtained. Further, the power transmission and the shaft seal system is confirmed to confidentially importantly contribute to the overall lifetime of the system. These techniques will help to improve the reliability of design of large scale machinery such as a plant.

Evaluation of Uncertainty Importance Measure in Fault Tree Analysis (결점나무 분석에서 불확실성 중요도 측도의 평가)

  • Cho, Jae-Gyeun;Jeong, Seok-Chan
    • The Journal of Information Systems
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    • v.17 no.3
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    • pp.25-37
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    • 2008
  • In a fault tree analysis, an uncertainty importance measure is often used to assess how much uncertainty of the top event probability (Q) is attributable to the uncertainty of a basic event probability ($q_i$), and thus, to identify those basic events whose uncertainties need to be reduced to effectively reduce the uncertainty of Q. For evaluating the measures suggested by many authors which assess a percentage change in the variance V of Q with respect to unit percentage change in the variance $v_i$ of $q_i$, V and ${\partial}V/{\partial}v_i$ need to be estimated analytically or by Monte Carlo simulation. However, it is very complicated to analytically compute V and ${\partial}V/{\partial}v_i$ for large-sized fault trees, and difficult to estimate them in a robust manner by Monte Carlo simulation. In this paper, we propose a method for evaluating the measure using discretization technique and Monte Carlo simulation. The proposed method provides a stable uncertainty importance of each basic event.

A Process Decomposition Strategy for Qualitative Fault Diagnosis of Large-scale Processes (대형공정의 정성적 이상진단을 위한 공정분할전략)

  • Lee Gibaek
    • Journal of the Korean Institute of Gas
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    • v.4 no.4 s.12
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    • pp.42-49
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    • 2000
  • Due to their size and complexity, it is very difficult to make diagnostic system for the whole chemical processes. Therefore, a systematic approach is required to decompose larpge-scale process into sub-processes and then diagnose them. This paper suggests a method for the minimization of knowledge base and flexible diagnosis to be used in qualitative fault diagnosis based on Fault-Effect Tree model. The system can be decomposed for flexible diagnosis, size reduction of knowledge base, and consistent construction of complex knowledge base. The new node, gate-variable, is introduced to connect the cause-effect relationships of each sub-process. For on-line diagnosis, off-line analysis is performed to construct Fault-Effect Trees of gate-variables as well as activation conditions of gate-variables. On-line diagnosis strategy is modified to get the same diagnosis result without system decomposition. The proposed method is illustrated with a fault diagnosis system for a large-scale boiler plant.

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A Study on the Alarm Processing System for Fossil Power Plant (화력발전소 경보처리 시스템에 관한 연구)

  • ;;;Zeungnam Bien
    • Journal of the Korean Institute of Telematics and Electronics B
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    • v.32B no.8
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    • pp.1045-1056
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    • 1995
  • The purpose of multiple alarm processing is to give the operator the correct information and perception of the malfunction present in the plant. In this thesis, an APS(Alarm Processing System) is studied for fossil power plants. This APS is based on a cause-consequence trees in the knowledge representation aspect for alarm and plant and adapts alarm filtering methods using fired time information in the decision aspect. Through the cause-consequence trees and filtering methods, the Alarm Processing System finds the cause alarm among the fired multiple alarms and calculates the cause degree which represents the possibility of a fault occurring in the instruments of the plant with the information of fired alarm. The knowledge base is built via interviews and questionaries with the expert operators on the Seoul power plant unit 4. Finally, the validity of the studied APS is shown via simulations.

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Analysis of the Effects of Subsystem Improvements on the Total System Safety (하부시스템의 안전도 개선이 전체 시스템 안전도에 미치는 영향 분석)

  • Yang, Hee-Joong
    • Journal of the Korea Safety Management & Science
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    • v.12 no.3
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    • pp.129-134
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    • 2010
  • 본 논문에서는 하부 안전 시스템의 개선이 전체 안전 시스템에 미치는 영향을 분석하기 위한 방법론을 개발하였다. 어느 하부 시스템의 안전성을 개선하느냐에 따라 전체 시스템의 안전성 증가는 서로 다르게 나타날 수도 있다. 본 연구에서는 베이지안 기법을 활용하여 사건가지와 상호연관도를 응용한 모형을 활용하였다. 또한 가지 파라메터의 확률 값 향상이 다음 번 사고까지의 시간을 어떻게 변화시키는지 연구하였다. 본 연구를 통해 우리가 관심을 갖고 있는 시스템 전체의 안전성 향상을 위해서는 어느 하부 시스템을 우선적으로 개선해야할지를 판단할 수 있게 한다.