Common Cause Failures: Extended Alpha Factor method and its Implementation

Size: px
Start display at page:

Download "Common Cause Failures: Extended Alpha Factor method and its Implementation"

Transcription

1 Common Cause Failures: Extended Alpha Factor method and its Implementation Alexandra Sitdikova Reactor Engineering Division, Jožef Stefan Institute Jamova 39, SI-1000 Ljubljana, Slovenia Institute of Physics and Technology, National Research Tomsk Polytechnic University, 30, Lenin Avenue, Tomsk, Russia ABSTRACT Marko Čepin Faculty of Electrical Engineering, University of Ljubljana Tržaška 25, SI-1000 Ljubljana, Slovenia Contribution of the common cause failures (CCFs) has been recognized as the dominant, within the results of a safety system reliability analysis and a probabilistic safety assessment (PSA) when analyzing nuclear safety. The purpose of this paper is to present a new method for explicit modeling of multiple components failure event within multiple common cause failure groups simultaneously. The method is based on Alpha Factor model with few modifications because of the developed expansion. The assessment for simultaneous assignment of single or multiple failure events to multiple common cause failure groups is performed. A standard standby safety system was selected as a case study and a comparison of results with standard Alpha Factor and Beta Factor methods was made. The results show that consideration of one failure event in several common cause failure groups gives a larger failure probability of considered systems. 1 INTRODUCTION Nuclear power plants are designed with redundant safety systems, redundant trains and redundant equipment for improved reliability and safety. However, very high reliability theoretically achievable through the use of redundancy is often compromised by single events that can ividually render redundant components unavailable [1]. Such events are known under the term common cause failure (CCF) events or common cause failures. CCF events have been recognized as the dominant contributors to the results of the system reliability analysis and the probabilistic safety assessment (PSA). They are defined as a subset of dependent failures in which two or more component fault states exist at the same time, or in short time interval, and thus they represent failures resulting from a shared cause [2]. For example, environmental CCFs include orbital debris strikes and exposure to excessively high humidity, temperature or vibration. Neglecting contribution of common caused failures can result a significant underestimation of risk. [3] CCFs are being acknowledged as one of the most challenging issues in the PSA, especially within PSA fault tree (FT) modeling of safety systems within nuclear power plants

2 520.2 This paper presents the method based on Alpha Factor method, but applying for explicit modeling of single and multiple components failure events simultaneously within number of several different Common Cause Failure Groups (CCFGs) sets. Each CCFG is defined on the basis of specific coupling mechanism. All sets could be sorted by the group size k (number of in it) and by the number of common in each CCFG, x (if it is single than x = 1 or multiple x 1; but in any case x k). The presented method that accommodates components failure events to be simultaneously assigned to different CCFGs given different coupling mechanisms is based on a modification of the well-known Alpha Factor model. The motivation for this study is the incapability of one of the most widespread PSA software for fault tree (FT) and event tree (ET) modeling, [5], for simultaneous assignment of neither one single component failure event, nor multiple components failure event in more than one CCFG within the fault tree analysis technique. Namely, the software package provides with a CCF modeling feature based on manual assignment of arbitrary failure events, i.e. basic events (BEs), to specific CCFG upon selection of proper parametric CCF model. In the process of this assignment of BE to CCFG, the software does not accommodate the option for one to assign one BE to several different CCFGs, a scenario quite probable in practice since given component can experience failure due to different causes, which if seen as shared causes couple the specific component with other components in different CCFGs simultaneously. The method was applied on a selected case study system. The application of the method enables improved PSA models. The improved models consequently implicate better results. 2 COMMON CAUSE FAILURE METHODS Three most known CCF methods include the Beta Factor, the Multi-Greek Letter (MGL) and the Alpha Factor method. The Beta Factor method is a single parameter method and assumes that whenever a CCF occurs, all components within a CCFG fail. Although historical nuclear ustry data icates that common caused events do not always fail all redundant components, the Beta Factor method does not allow consideration of intermediate failure criteria (e.g., 2 of 3 failures leading to a specific failure). The MGL and Alpha Factor methods are more detailed and allow consideration of intermediate failure criteria. That is for large number of redundant components, many possible failure scenarios exist and extensive modeling efforts are required in order to depict all possible failure combinations. Practicality necessitates some simplification, especially for large CCFG sizes and components with high degrees of redundancy [2]. 2.1 Alpha Factor Method Several guidelines for modeling CCFs in PSA have been published [1, 2, 3]. Some give the sources of generic common caused data. This data is presented in the form of Alpha Factor fractions of the total frequency (α n ) in tables for use with CCFG size up to eight. For a given component group size k, an ividual is the probability that when a CCF occurs, it involves failure of exactly n of k components. The sum of these fractions for a single CCFG is equal to one. The probability of CCF event involving 'n' specific components (1 n k) in CCFG of size 'k' for non-staggered testing scheme, is calculated by using the following equation: (1) (2)

3 520.3 By equation (2) the normalizing factor is calculated. Then, is the probability of an ependent failure of a single component. is the total probability of failure for a given component. Therefore, represents a CCF multiplier, often shown as a percentage, intended to be multiplied by the component failure rate for PSA fault tree CCF basic event data entry. These CCF multipliers are calculated for each CCF criteria in a CCFG. The system failure probability is also calculated. Analyzing a system S made of three components A, B, C, where system failure probability of two-out-of-three components, with Alpha factor method is given by Eq. (3): (3) where P(S) failure probability system S; P(A), P(B), P(C) - failure probability of component A, B and C respectively; P(C AB ) - failure probability of two component failures: A and B, common cause; P(C ABC ) - failure probability of three component failures: A, B and C, common cause. The failure probability of a system S depends on failure probability of its components and on the contribution of common cause failures, which are modeled as one common cause group consisting of components A, B and C, which may fail due to common cause. Alpha facto method considers cases where two of three components fail due to common mechanism or all three components fail due to common mechanism. It is assumed that failure probabilities of similar components are the same. (4) (5) (6) The probability of occurrence of any basic event within a given common cause component group is assumed to depend only on the number and not on the specific components in that basic event. Using the above notation, the system failure probability can be written as: (7) This method was developed for system with three components considering one CCFG. For cases of multiple CCFG simultaneously, the modified Alpha Factor method is proposed. 2.2 Modified Alpha Factor Method The method is based on traditional Alpha Factor Method with few modifications because of expansion for multiple CCFGs defined for a system. The extension goes by number of groups in every set and number of common. In parallel system of four trains, the function of one is enough for the system success, so all trains should fail for the system failure, i.e. the failure criteria is n out of n. In order to present briefly how the modified Alpha Factor model works, let us assume an example system with four trains as presented on the Figure 1. The success criteria is 1/4, the failure criteria is 4/4. A1 A2 A3 B1 B2 B3 C1 C2 C3 D1 D2 D3 Figure 1: Example system with four trains

4 520.4 The fault tree without implementation of CCF is shown on Figure 2 and the one with CCF implementation on Figure 3. TOP A B C D A1 A2 A3 B1 B2 B3 C1 C2 C3 D1 D2 D3 Figure 2: Fault tree without CCF implementation TOP CCF Indep. CCFG 4 Component A Fails Component B Fails Component C Fails Component D Fails A_ CCFG 2 CCFG 3 B_ CCFG 2 CCFG 3 C_ CCFG 2 CCFG 3 D_ CCFG 2 CCFG 3 A1_ A2_ A3_ B1_ B2_ B3_ C1_ C2_ C3_ D1_ D2_ D3_ Figure 3: Fault tree with CCF implementation One common mechanism is found for components A1, B1, C1 and D1, which is modeled in one CCFG. The other common mechanism is found for components: A1, B2, C2 and D2, which is modeled in other CCFG. The size k = 4 (Figure 4) means the number of components in a group. The probability of a set failure, concerning Boolean logic, could be calculated as a sum of all combinations of two, three and four element failures and ependent failure of element A1: 12 A1B1, A1C1, A1D1, B1C1, B1D1, C1D1, A1B2, A1C2, A1D2, B2C2, B2D2, C2D2; 8 A1B1C1, A1B1D1, A1C1D1, B1C1D1, A1B2C2, A1B2D2, A1C2D2, B2C2D2;

5 A1B1C1D1, A1B2C2D2; Summarizing, the probability of failure for given set could be defined as:, or (8) (9) where - number of combinations n of k,. P ependent failure probability of a component; P 2CF - failure probability of two component failures due to common cause; P 3CF - failure probability of three component failures due to common cause; P 4CF - failure probability of four component failures due to common cause. Figure 4: Example system with two CCFGs: A1B1C1D1, A1B2C2D2 Thus, the probability of failure for m-set Ps with single common component in it is calculated as follows. One more way of applying modified Alpha Factor method is to use the sets with more than one common element in CCFGs. The probability of multiple failure events in multiple common cause failure groups is calculated in this case. The probability of failure of a set with x common components in it (size k > x) could be described with the following equation: (11) where the probability of ependent failures, sum of probabilities of each common component (A1, B1, C1, etc.). The main difference in comparison with usual Alpha factor method is the way of calculation probabilities of the basic events involving n specific components in a CCFG of size k (1 n k), or : (12) This method is proposed for cases, where the set contains the groups with similar types of components in one train (i.e. diesel generators, check valves, motor pumps), where all component failure probabilities are equal. For component groups of different types of components, where several failure probabilities are used, the mean value of normalizing factor and failure frequency of each component are calculated as follows.,, (13) (14) (10) (15)

6 520.6 So the probability of common cause failure involving n specific components in CCFG can now be written as: (16) 3 CASE STUDY A simplified model of an auxiliary feedwater system (AFWS) of a light-water PWR second generation NPP was used for a case study (Figure 5). The AFWS provides a backup supply of feedwater to the secondary side of the steam generators when the main feedwater pumps cease to operate that makes the normal main feedwater unavailable [4], [5]. SG 1 MIV 7 CV 7 CV 4 CV 1 MIV 1 MIV 9 FCV 1 MIV 4 MDP 1 CV 9 MIV 12 MIV_CS 1 CST 1 POIV 2 FCV 3 MIV 5 CV 5 TDP CV 2 MIV 2 FCV 4 SG 2 CV 10 POIV 1 MIV 11 MIV_CS 2 CST 2 MIV 10 FCV 2 MIV 8 CV 8 MIV 6 CV 6 MDP 2 CV 3 MIV 3 Figure 5: Auxiliary Feedwater System (AFWS) The corresponding FT top event is defined as system failure. AFWS is nonoperational if either one of the two steam generators does not receive cooling water. The presented method for assigning single component failure within different CCFGs simultaneously was applied. Two categories of AFWS components were encompassed by the method, i.e. check valves (CVs) and isolation valves (MIVs). These components were combined, first, into groups and then to several sets by size. For calculation the probability of sets failure were used Modified Alpha Factor method, Alpha Factor method and Beta Factor method. The following Table 1 and Table 2 present the value of probabilities of a CCF involving n components in CCFG size k. Notation CV# means failure of check valve #. Notation MIV# means failure of isolation valve #. Table 1: Value of P ncf for Modified Alpha Factor method

7 520.7 CVs Sets P IND P 2CF P 3CF P 4CF P S CV1CV6, CV1CV8 8,79E-05 1,21E-05 1,00E-04 CV1CV4CV7,CV1CV2CV3 8,40E-05 2,33E-05 5,51E-06 1,13E-04 CV1CV5CV9CV10 8,13E-05 2,18E-05 5,39E-06 1,85E-06 1,09E-04 MIVs Sets P IND P 2CF P 3CF P SUM MIV4, MIV10; MIV4, MIV9 9,55E-05 2,27E-06 9,77E-05 MIV4, MIV5, MIV6; MIV4, MIV1, MIV7; MIV4, MIV11, MIV12 9,33E-05 1,51E-05 3,29E-06 1,12E-04 Table 2: Value of P ncf for Alpha Factor method CVs Sets P IND P 2CF P 3CF P 4CF P S CV1CV6, CV1CV8 1,76E-04 2,42E-05 2,00E-04 CV1CV4CV7, CV1CV2CV3 2,52E-04 7,76E-06 1,65E-05 2,76E-04 CV1CV5CV9CV10 3,25E-04 2,43E-06 1,35E-06 7,40E-06 3,36E-04 MIVs Sets P IND P 2CF P 3CF P SUM MIV4, MIV10; MIV4, MIV9 1,91E-04 9,07E-06 2,00E-04 MIV4, MIV5, MIV6; MIV4, MIV1, MIV7; MIV4, MIV11, MIV12 2,80E-04 5,05E-06 9,86E-06 2,95E-04 Table 3: Results comparison for applied CCF methods Modified Alpha factor Alpha factor Method Beta factor Method Method P CV1 3,21E-04 8,12E-04 1,00E-04 P MIV4 2,09E-04 4,95E-04 1,00E-04 P TOP2 2,45E-04 2,69E-04 2,88E-04 Table 3 comprises the comparison of results for applied methods of calculation CCF, considering TOP event and two categories of AFWS components check valves and isolation valves. Due to the fact that Alpha Factor modeling techniques more failure combinations, the meaning of failure probability could be two to three orders higher than for Beta Factor method. The modified Alpha Factor method gives good results, what can let use it for CCF analysis. 4 CONCLUSION The modified Alpha Factor method for CCF analysis and prevention has been examined to show that it is useful for assessment the potential CCF at nuclear power plants. This method will help calculate probabilities of single and multiple events components failure events simultaneously within number of several different CCFGs, combined in set. Proposed method has several differences from standard Alpha Factor method. It can be seen as its upgrade. The main advantage of the discussed model is fact that implementation of such CCF approach could be especially useful for CCFG within several numbers of

8 520.8 different types of components. Examples include number of system trains with components placed in one room or on the same floor, the number of similar components of the same producer with the same physical and technological characteristics. The proposed method presents the explicit modeling of CCF. The disadvantage is associated with the fact that it requires more specific calculations for several parameters which is connected with more efforts and more data, which may lead to a higher uncertainty. ACKNOWLEDGMENTS The Slovenian Research Agency supported this research (project J2-2182). REFERENCES [1] Mosleh A., Parry G.W., Paula H.M., Worledge D. H., Rasmuson D. M. Procedures for treating common cause failures in safety and reliability studies. NUREG/CR-4780, Vol.1. US NRC, 1981; Washington, DC. [2] Mosleh A., Parry G.W., Paula H.M., Worledge D. H., Rasmuson D. M. Procedures for treating common cause failures in safety and reliability studies. NUREG/CR-4780, Vol.2. US NRC, 1989; Washington, DC. [3] Mosleh A., Rasmuson D.M., Marshall F.M. Guidelines on modelling common-cause failures in PRA. NUREG/CR US NRC, 1998; Washington, DC. [4] Čepin M. Optimization of safety equipment improves safety. Reliability Engineering and System Safety 2002; pp [5] Kančev D., Čepin M. Common Cause Failures: Explicit modelling of single failure event within different common cause groups, Proceedings of NENE201, NSS, [6] Čepin M., Application of common cause analysis for assessment of reliability of power systems, Proc. of 2010 IEEE PMAPS Conf., Singapore, June 14-17, 2010, pp

Presentation of Common Cause Failures in Fault Tree Structure of Krško PSA: An Historical Overview

Presentation of Common Cause Failures in Fault Tree Structure of Krško PSA: An Historical Overview International Conference Nuclear Energy for New Europe 2003 Portorož, Slovenia, September 8-11, 2003 http://www.drustvo-js.si/port2003 Presentation of Common Cause Failures in Fault Tree Structure of Krško

More information

Time Dependent Analysis with Common Cause Failure Events in RiskSpectrum

Time Dependent Analysis with Common Cause Failure Events in RiskSpectrum Time Dependent Analysis with Common Cause Failure Events in RiskSpectrum Pavel Krcal a,b and Ola Bäckström a a Lloyd's Register Consulting, Stockholm, Sweden b Uppsala University, Uppsala, Sweden Abstract:

More information

Modeling Common Cause Failures in Diverse Components with Fault Tree Applications

Modeling Common Cause Failures in Diverse Components with Fault Tree Applications Modeling Common Cause Failures in Diverse s with Fault Tree Applications Joseph R. Belland, Isograph Inc. Key Words: Common Cause Failures, Fault Trees, Beta Factor SUMMARY & CONCLUSIONS A common cause

More information

Reliability of Technical Systems

Reliability of Technical Systems Reliability of Technical Systems Main Topics. Short Introduction, Reliability Parameters: Failure Rate, Failure Probability, etc. 2. Some Important Reliability Distributions 3. Component Reliability 4.

More information

A General Cause Based Methodology for Analysis of Common Cause and Dependent Failures in System Risk and Reliability Assessments

A General Cause Based Methodology for Analysis of Common Cause and Dependent Failures in System Risk and Reliability Assessments A General Cause Based Methodology for Analysis of Common Cause and Dependent Failures in System Risk and Reliability Assessments Andrew O Connor a*, Ali Mosleh b a1 Center for Risk and Reliability, University

More information

AP1000 European 19. Probabilistic Risk Assessment Design Control Document

AP1000 European 19. Probabilistic Risk Assessment Design Control Document 19.15 Chemical and Volume Control System 19.15.1 System Description See subsection 9.3.6.2. 19.15.2 System Operation See subsection 9.3.6.4. 19.15.3 Performance during Accident Conditions See subsection

More information

ASSESSMENT OF DYNAMIC PRA TECHNIQUES WITH INDUSTRY- AVERAGE COMPONENT PERFORMANCE DATA

ASSESSMENT OF DYNAMIC PRA TECHNIQUES WITH INDUSTRY- AVERAGE COMPONENT PERFORMANCE DATA ASSESSMENT OF DYNAMIC PRA TECHNIQUES WITH INDUSTRY- AVERAGE COMPONENT PERFORMANCE DATA Vaibhav Yadav*, Vivek Agarwal, Andrei V. Gribok, and Curtis L. Smith Idaho National Laboratory 2525 Fremont Avenue,

More information

Evaluating the Core Damage Frequency of a TRIGA Research Reactor Using Risk Assessment Tool Software

Evaluating the Core Damage Frequency of a TRIGA Research Reactor Using Risk Assessment Tool Software Evaluating the Core Damage Frequency of a TRIGA Research Reactor Using Risk Assessment Tool Software M. Nematollahi and Sh. Kamyab Abstract After all preventive and mitigative measures considered in the

More information

Fault Tree Modeling Using CBHRA and SAF Method. Korea Atomic Energy Research Institute Hyun Gook Kang

Fault Tree Modeling Using CBHRA and SAF Method. Korea Atomic Energy Research Institute Hyun Gook Kang Fault Tree Modeling Using CBHRA and SAF Method Korea Atoic Energy Research Institute Hyun Goo Kang Contents 1 2 Introduction Siplified Alpha Factor Method 3 Condition-based HRA Method Case Study 5 Conclusions

More information

RISK-INFORMED OPERATIONAL DECISION MANAGEMENT (RIODM): RISK, EVENT TREES AND FAULT TREES

RISK-INFORMED OPERATIONAL DECISION MANAGEMENT (RIODM): RISK, EVENT TREES AND FAULT TREES 22.38 PROBABILITY AND ITS APPLICATIONS TO RELIABILITY, QUALITY CONTROL AND RISK ASSESSMENT Fall 2005, Lecture 1 RISK-INFORMED OPERATIONAL DECISION MANAGEMENT (RIODM): RISK, EVENT TREES AND FAULT TREES

More information

Development of Multi-Unit Dependency Evaluation Model Using Markov Process and Monte Carlo Method

Development of Multi-Unit Dependency Evaluation Model Using Markov Process and Monte Carlo Method Development of Multi-Unit Dependency Evaluation Model Using Markov Process and Monte Carlo Method Sunghyon Jang, and Akira Yamaguchi Department of Nuclear Engineering and Management, The University of

More information

Analyzing system changes with importance measure pairs: Risk increase factor and Fussell-Vesely compared to Birnbaum and failure probability

Analyzing system changes with importance measure pairs: Risk increase factor and Fussell-Vesely compared to Birnbaum and failure probability Analyzing system changes with importance measure pairs: Risk increase factor and Fussell-Vesely compared to Birnbaum and failure probability Janne Laitonen*, Ilkka Niemelä Radiation and Nuclear Safety

More information

Application of Common Cause Failure Methodology to Aviation Safety Assessment Model

Application of Common Cause Failure Methodology to Aviation Safety Assessment Model Application of Common Cause Failure Methodology to Aviation Safety Assessment Model Seungwon Noh Systems Engineering and Operations Research George Mason University Fairfax, VA, USA snoh2@gmu.edu Abstract

More information

Quantitative Reliability Analysis

Quantitative Reliability Analysis Quantitative Reliability Analysis Moosung Jae May 4, 2015 System Reliability Analysis System reliability analysis is conducted in terms of probabilities The probabilities of events can be modelled as logical

More information

Common Cause Failure (CCF)

Common Cause Failure (CCF) Common Cause Failure (CCF) 건국대학교컴퓨터공학과 UC Lab. 정혁준 & 박경식 amitajung@naver.com, kyeongsik@konkuk.ac.kr Contents Common Cause Failure (CCF) Types of CCF Examples Reducing CCF Common Cause Failure (CCF) Definition

More information

CHAPTER 3 BOOLEAN ALGEBRA

CHAPTER 3 BOOLEAN ALGEBRA CHAPTER 3 BOOLEAN ALGEBRA (continued) This chapter in the book includes: Objectives Study Guide 3.1 Multiplying Out and Factoring Expressions 3.2 Exclusive-OR and Equivalence Operations 3.3 The Consensus

More information

Fault Tree Modeling for Redundant Multi-Functional Digital Systems

Fault Tree Modeling for Redundant Multi-Functional Digital Systems International Journal of Perforability Engineering, Vol. 3, No. 3, July, 2007, pp. 329-336 RAMS Consultants Printed in India Fault Tree Modeling for Redundant Multi-Functional Digital Systes HYUN GOOK

More information

Module No. # 03 Lecture No. # 11 Probabilistic risk analysis

Module No. # 03 Lecture No. # 11 Probabilistic risk analysis Health, Safety and Environmental Management in Petroleum and offshore Engineering Prof. Dr. Srinivasan Chandrasekaran Department of Ocean Engineering Indian Institute of Technology, Madras Module No. #

More information

Issues in Dependency Modeling in Multi- Unit Seismic PRA

Issues in Dependency Modeling in Multi- Unit Seismic PRA Issues in Dependency Modeling in Multi- Unit Seismic PRA 1 Taotao Zhou Mohammad Modarres Enrique López Droguett Center for Risk and Reliability University of Maryland, College Park Presented at the PSA-2017,

More information

Availability analysis of nuclear power plant system with the consideration of logical loop structures

Availability analysis of nuclear power plant system with the consideration of logical loop structures Availability analysis of nuclear power plant system with the consideration of logical loop structures MATSUOKA Takeshi 1, 2 1. Mechanical Systems Engineering, Department of Engineering, Utsunomiya University,

More information

Computer Organization I. Lecture 13: Design of Combinational Logic Circuits

Computer Organization I. Lecture 13: Design of Combinational Logic Circuits Computer Organization I Lecture 13: Design of Combinational Logic Circuits Overview The optimization of multiple-level circuits Mapping Technology Verification Objectives To know how to optimize the multiple-level

More information

Risk Analysis of Highly-integrated Systems

Risk Analysis of Highly-integrated Systems Risk Analysis of Highly-integrated Systems RA II: Methods (FTA, ETA) Fault Tree Analysis (FTA) Problem description It is not possible to analyse complicated, highly-reliable or novel systems as black box

More information

Study on Quantification Methodology of accident sequences for Tsunami Induced by Seismic Events.

Study on Quantification Methodology of accident sequences for Tsunami Induced by Seismic Events. Study on Quantification Methodology of accident sequences for Tsunami Induced by Seismic Events 1 Keisuke Usui, 2 Hitoshi Muta, 3 Ken Muramatsu 1 Graduate Student, Corporative Major in Nuclear Energy:

More information

Advanced Digital Design with the Verilog HDL, Second Edition Michael D. Ciletti Prentice Hall, Pearson Education, 2011

Advanced Digital Design with the Verilog HDL, Second Edition Michael D. Ciletti Prentice Hall, Pearson Education, 2011 Problem 2-1 Recall that a minterm is a cube in which every variable appears. A Boolean expression in SOP form is canonical if every cube in the expression has a unique representation in which all of the

More information

A Computer Program for Evaluating the Alpha Factor Model Parameters Using the Bayesian Operation

A Computer Program for Evaluating the Alpha Factor Model Parameters Using the Bayesian Operation Computer Program for Evaluating the lpha actor odel Parameters Using the Bayesian Operation Baehyeuk Kwon a, oosung Jae a*, and Dong Wook Jerng b a Department of Nuclear Engineering, Hanyang University

More information

Lecture 6: Manipulation of Algebraic Functions, Boolean Algebra, Karnaugh Maps

Lecture 6: Manipulation of Algebraic Functions, Boolean Algebra, Karnaugh Maps EE210: Switching Systems Lecture 6: Manipulation of Algebraic Functions, Boolean Algebra, Karnaugh Maps Prof. YingLi Tian Feb. 21/26, 2019 Department of Electrical Engineering The City College of New York

More information

Multi-Unit Nuclear Plant Risks and Implications of the Quantitative Health Objectives

Multi-Unit Nuclear Plant Risks and Implications of the Quantitative Health Objectives Multi-Unit Nuclear Plant Risks and Implications of the Quantitative Health Objectives Presented at the International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA2015) April 27,

More information

Overview of Control System Design

Overview of Control System Design Overview of Control System Design General Requirements 1. Safety. It is imperative that industrial plants operate safely so as to promote the well-being of people and equipment within the plant and in

More information

CHAPTER 5 KARNAUGH MAPS

CHAPTER 5 KARNAUGH MAPS CHAPTER 5 1/36 KARNAUGH MAPS This chapter in the book includes: Objectives Study Guide 5.1 Minimum Forms of Switching Functions 5.2 Two- and Three-Variable Karnaugh Maps 5.3 Four-Variable Karnaugh Maps

More information

12 - The Tie Set Method

12 - The Tie Set Method 12 - The Tie Set Method Definitions: A tie set V is a set of components whose success results in system success, i.e. the presence of all components in any tie set connects the input to the output in the

More information

System Reliability Thory 6. Common-Cause Failures

System Reliability Thory 6. Common-Cause Failures System Reliability Thory 6. Common-Cause Failures Marvin Rausand marvin.rausand@ntnu.no RAMS Group Department of Production and Quality Engineering NTNU (Version 0.1) Marvin Rausand (RAMS Group) System

More information

Causal & Frequency Analysis

Causal & Frequency Analysis Causal & Frequency Analysis Arshad Ahmad arshad@utm.my Fishbone Diagram 2 The Cause and Effect (CE) Diagram (Ishikawa Fishbone) Created in 1943 by Professor Kaoru Ishikawa of Tokyo University Used to investigate

More information

Session 3 Fractional Factorial Designs 4

Session 3 Fractional Factorial Designs 4 Session 3 Fractional Factorial Designs 3 a Modification of a Bearing Example 3. Fractional Factorial Designs Two-level fractional factorial designs Confounding Blocking Two-Level Eight Run Orthogonal Array

More information

Safety and Reliability of Embedded Systems

Safety and Reliability of Embedded Systems (Sicherheit und Zuverlässigkeit eingebetteter Systeme) Fault Tree Analysis Mathematical Background and Algorithms Prof. Dr. Liggesmeyer, 0 Content Definitions of Terms Introduction to Combinatorics General

More information

PROBABILISTIC AND POSSIBILISTIC FAULT TREE ANALYSIS

PROBABILISTIC AND POSSIBILISTIC FAULT TREE ANALYSIS PROBABILISTIC AD POSSIBILISTIC FAULT TREE AALYSIS M. Ragheb 12/28/2017 ITRODUCTIO In the design of nuclear power plants, it is important to analyze the probable and possible mechanisms of failure. Fault

More information

Karnaugh Maps Objectives

Karnaugh Maps Objectives Karnaugh Maps Objectives For Karnaugh Maps of up to 5 variables Plot a function from algebraic, minterm or maxterm form Obtain minimum Sum of Products and Product of Sums Understand the relationship between

More information

Chapter 18 Section 8.5 Fault Trees Analysis (FTA) Don t get caught out on a limb of your fault tree.

Chapter 18 Section 8.5 Fault Trees Analysis (FTA) Don t get caught out on a limb of your fault tree. Chapter 18 Section 8.5 Fault Trees Analysis (FTA) Don t get caught out on a limb of your fault tree. C. Ebeling, Intro to Reliability & Maintainability Engineering, 2 nd ed. Waveland Press, Inc. Copyright

More information

Chapter 5. System Reliability and Reliability Prediction.

Chapter 5. System Reliability and Reliability Prediction. Chapter 5. System Reliability and Reliability Prediction. Problems & Solutions. Problem 1. Estimate the individual part failure rate given a base failure rate of 0.0333 failure/hour, a quality factor of

More information

ARTICLE. Downloaded by [Harbin Engineering University] at 18:58 14 June 2013

ARTICLE. Downloaded by [Harbin Engineering University] at 18:58 14 June 2013 Journal of Nuclear Science and Technology, 2013 Vol. 50, No. 7, 695 708, http://dx.doi.org/10.1080/00223131.2013.790304 ARTICLE Considerations of uncertainties in evaluating dynamic reliability by GO-FLOW

More information

Karnaugh Map & Boolean Expression Simplification

Karnaugh Map & Boolean Expression Simplification Karnaugh Map & Boolean Expression Simplification Mapping a Standard POS Expression For a Standard POS expression, a 0 is placed in the cell corresponding to the product term (maxterm) present in the expression.

More information

Experiment for Justification the Reliability of Passive Safety System in NPP

Experiment for Justification the Reliability of Passive Safety System in NPP XIII International Youth Scientific and Practical Conference FUTURE OF ATOMIC ENERGY - AtomFuture 2017 Volume 2017 Conference Paper Experiment for Justification the Reliability of Passive Safety System

More information

Risk-informed Maintenance for Non-coherent Systems

Risk-informed Maintenance for Non-coherent Systems Risk-informed Maintenance for Non-coherent Systems by Ye Tao A Thesis Submitted in Partial Fulfillment of the Requirements for the Degree of Master of Applied Science In The Faculty of the Engineering

More information

A BAYESIAN SOLUTION TO INCOMPLETENESS

A BAYESIAN SOLUTION TO INCOMPLETENESS A BAYESIAN SOLUTION TO INCOMPLETENESS IN PROBABILISTIC RISK ASSESSMENT 14th International Probabilistic Safety Assessment & Management Conference PSAM-14 September 17-21, 2018 Los Angeles, United States

More information

Chapter 3. Boolean Algebra. (continued)

Chapter 3. Boolean Algebra. (continued) Chapter 3. Boolean Algebra (continued) Algebraic structure consisting of: set of elements B binary operations {+, -} unary operation {'} Boolean Algebra such that the following axioms hold:. B contains

More information

Basic notions of probability theory

Basic notions of probability theory Basic notions of probability theory Contents o Boolean Logic o Definitions of probability o Probability laws Objectives of This Lecture What do we intend for probability in the context of RAM and risk

More information

Lecture 5: NAND, NOR and XOR Gates, Simplification of Algebraic Expressions

Lecture 5: NAND, NOR and XOR Gates, Simplification of Algebraic Expressions EE210: Switching Systems Lecture 5: NAND, NOR and XOR Gates, Simplification of Algebraic Expressions Prof. YingLi Tian Feb. 15, 2018 Department of Electrical Engineering The City College of New York The

More information

PSA on Extreme Weather Phenomena for NPP Paks

PSA on Extreme Weather Phenomena for NPP Paks PSA on Extreme Weather Phenomena for NPP Paks Tamás Siklóssy siklossyt@nubiki.hu WGRISK Technical Discussion on PSA Related to Weather-Induced Hazards Paris, 9 March, 2017 Background Level 1 Seismic PSA

More information

SITRON: Site risk assessment approach developed for Nordic countries Ola Bäckström

SITRON: Site risk assessment approach developed for Nordic countries Ola Bäckström SITRON: Site risk assessment approach developed for Nordic countries Ola Bäckström, Erik Cederhorn, Xuhong He, Jan-Erik Holmberg, Tero Tyrväinen 13 September 2017 SITRON (SITe Risk Of Nuclear installations)

More information

Assessing system reliability through binary decision diagrams using bayesian techniques.

Assessing system reliability through binary decision diagrams using bayesian techniques. Loughborough University Institutional Repository Assessing system reliability through binary decision diagrams using bayesian techniques. This item was submitted to Loughborough University's Institutional

More information

Seismic Issues for California's Nuclear Power Plants. Norman Abrahamson University of California, Berkeley

Seismic Issues for California's Nuclear Power Plants. Norman Abrahamson University of California, Berkeley Seismic Issues for California's Nuclear Power Plants Norman Abrahamson University of California, Berkeley From UCERF 2 Seismic Setting for California s Nuclear Power Plants Major Offshore Strike-Slip Faults

More information

Reliability of sequential systems using the causeconsequence diagram method

Reliability of sequential systems using the causeconsequence diagram method Loughborough University Institutional Repository Reliability of sequential systems using the causeconsequence diagram method This item was submitted to Loughborough University's Institutional Repository

More information

STEAM GENERATOR TUBES RUPTURE PROBABILITY ESTIMATION - STUDY OF THE AXIALLY CRACKED TUBE CASE

STEAM GENERATOR TUBES RUPTURE PROBABILITY ESTIMATION - STUDY OF THE AXIALLY CRACKED TUBE CASE XN9500220 STEAM GENERATOR TUBES RUPTURE PROBABILITY ESTIMATION - STUDY OF THE AXIALLY CRACKED TUBE CASE B.Mavko, L.Cizelj "Jozef Stefan" Institute, Jamova 39, 61111 Ljubljana, Slovenia G.Roussel AIB-Vingotte

More information

UNIT 3 BOOLEAN ALGEBRA (CONT D)

UNIT 3 BOOLEAN ALGEBRA (CONT D) UNIT 3 BOOLEAN ALGEBRA (CONT D) Spring 2011 Boolean Algebra (cont d) 2 Contents Multiplying out and factoring expressions Exclusive-OR and Exclusive-NOR operations The consensus theorem Summary of algebraic

More information

SIMPLE METHOD TO ACCOUNT FOR THE STATE OF KNOWLEDGE CORRELATION

SIMPLE METHOD TO ACCOUNT FOR THE STATE OF KNOWLEDGE CORRELATION SIMPLE METHOD TO ACCOUNT FOR THE STATE OF KNOWLEDGE CORRELATION PSA 017, Pittsburgh, PA September 017 Michael Lloyd (MLloyd@RiskInformedSolutions.com) Risk Informed Solutions Consulting Services, Inc.

More information

Uncertainty Analysis on Containment Failure Frequency for a Japanese PWR Plant

Uncertainty Analysis on Containment Failure Frequency for a Japanese PWR Plant Uncertainty Analysis on Containment Failure Frequency for a Japanese PWR Plant O. KAWABATA Environmental Safety Analysis Group Safety Analysis and Evaluation Division, Japan Nuclear Energy Safety Organization

More information

Failures in Process Industries

Failures in Process Industries Fault Tree Analysis Failures in Process Industries Single Component Failure Data for failure rates are compiled by industry Single component or single action Multiple Component Failure Failures resulting

More information

Risk Analysis Framework for Severe Accident Mitigation Strategy in Nordic BWR: An Approach to Communication and Decision Making

Risk Analysis Framework for Severe Accident Mitigation Strategy in Nordic BWR: An Approach to Communication and Decision Making International Topical Meeting on Probabilistic Safety Assessment And Analysis, PSA 2017, September 24-28, 2017. Pittsburgh, PA. Risk Analysis Framework for Severe Accident Mitigation Strategy in Nordic

More information

Lecture 5 Probability

Lecture 5 Probability Lecture 5 Probability Dr. V.G. Snell Nuclear Reactor Safety Course McMaster University vgs 1 Probability Basic Ideas P(A)/probability of event A 'lim n64 ( x n ) (1) (Axiom #1) 0 # P(A) #1 (1) (Axiom #2):

More information

Reliability of Technical Systems

Reliability of Technical Systems Reliability of Technical Systems Main Topics 1. Short Introduction, Reliability Parameters: Failure Rate, Failure Probability, etc. 2. Some Important Reliability Distributions 3. Component Reliability

More information

We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists. International authors and editors

We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists. International authors and editors We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists 3,500 108,000 1.7 M Open access books available International authors and editors Downloads Our

More information

1. INTRODUCTION Japan c Osaka University; 2-1 Yamada-oka, Suita, Osaka, Japan

1. INTRODUCTION Japan c Osaka University; 2-1 Yamada-oka, Suita, Osaka, Japan Development of Margin Assessment Methodology of Decay Heat Removal Function Against External Hazards Project Overview and Preliminary Risk Assessment Against Snow Hidemasa Yamano a,*, Hiroyuki Nishino

More information

ANALYSIS OF INDEPENDENT PROTECTION LAYERS AND SAFETY INSTRUMENTED SYSTEM FOR OIL GAS SEPARATOR USING BAYESIAN METHODS

ANALYSIS OF INDEPENDENT PROTECTION LAYERS AND SAFETY INSTRUMENTED SYSTEM FOR OIL GAS SEPARATOR USING BAYESIAN METHODS ANALYSIS OF INDEPENDENT PROTECTION LAYERS AND SAFETY INSTRUMENTED SYSTEM FOR OIL GAS SEPARATOR USING BAYESIAN METHODS G. Unnikrishnan 1 *, Shrihari 2, Nihal A. Siddiqui 3 1 Department of Health, Safety

More information

COMPARE OF THE EMPIRICAL AND NUMERICAL TSUNAMI HAZARD ASSESSMENT RESULTS FOR THE EAST COAST OF KOREA. Min Kyu Kim 1, In-kil Choi 2

COMPARE OF THE EMPIRICAL AND NUMERICAL TSUNAMI HAZARD ASSESSMENT RESULTS FOR THE EAST COAST OF KOREA. Min Kyu Kim 1, In-kil Choi 2 COMPARE OF THE EMPIRICAL AND NUMERICAL TSUNAMI HAZARD ASSESSMENT RESULTS FOR THE EAST COAST OF KOREA Min Kyu Kim 1, In-kil Choi 2 1 Korea Atomic Energy Research Institute: 989-111 Daedeok-Daero Youseong

More information

Analysis methods for fault trees that contain secondary failures

Analysis methods for fault trees that contain secondary failures Loughborough University Institutional Repository Analysis methods for fault trees that contain secondary failures This item was submitted to Loughborough University's Institutional Repository by the/an

More information

Chapter 6. a. Open Circuit. Only if both resistors fail open-circuit, i.e. they are in parallel.

Chapter 6. a. Open Circuit. Only if both resistors fail open-circuit, i.e. they are in parallel. Chapter 6 1. a. Section 6.1. b. Section 6.3, see also Section 6.2. c. Predictions based on most published sources of reliability data tend to underestimate the reliability that is achievable, given that

More information

of an algorithm for automated cause-consequence diagram construction.

of an algorithm for automated cause-consequence diagram construction. Loughborough University Institutional Repository Development of an algorithm for automated cause-consequence diagram construction. This item was submitted to Loughborough University's Institutional Repository

More information

UNIT 5 KARNAUGH MAPS Spring 2011

UNIT 5 KARNAUGH MAPS Spring 2011 UNIT 5 KRNUGH MPS Spring 2 Karnaugh Maps 2 Contents Minimum forms of switching functions Two- and three-variable Four-variable Determination of minimum expressions using essential prime implicants Five-variable

More information

State Nuclear Power Technology Research & Development Center, Beijing, China

State Nuclear Power Technology Research & Development Center, Beijing, China Passive system Evaluation by using integral thermal-hydraulic test facility in passive NPP(nuclear power plant) PSA(probabilistic safety assessment) process Ruichang Zhao a, Huajian Chang a, Yang Xiang

More information

PSA Quantification. Analysis of Results. Workshop Information IAEA Workshop

PSA Quantification. Analysis of Results. Workshop Information IAEA Workshop IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making PSA Quantification. Analysis of Results Lecturer Lesson Lesson IV IV 3_7.3 3_7.3 Workshop Information IAEA Workshop City, XX

More information

Geometry Problem Solving Drill 08: Congruent Triangles

Geometry Problem Solving Drill 08: Congruent Triangles Geometry Problem Solving Drill 08: Congruent Triangles Question No. 1 of 10 Question 1. The following triangles are congruent. What is the value of x? Question #01 (A) 13.33 (B) 10 (C) 31 (D) 18 You set

More information

Safety and Reliability of Embedded Systems. (Sicherheit und Zuverlässigkeit eingebetteter Systeme) Fault Tree Analysis Obscurities and Open Issues

Safety and Reliability of Embedded Systems. (Sicherheit und Zuverlässigkeit eingebetteter Systeme) Fault Tree Analysis Obscurities and Open Issues (Sicherheit und Zuverlässigkeit eingebetteter Systeme) Fault Tree Analysis Obscurities and Open Issues Content What are Events? Examples for Problematic Event Semantics Inhibit, Enabler / Conditioning

More information

This case study also provides recommendations for future lightning protection design for existing (brownfield) substation.

This case study also provides recommendations for future lightning protection design for existing (brownfield) substation. A Case Study for Substation Lightning Strike Risk Evaluation Stephen Chuang 111 Dunsmuir Street #400, Vancouver, BC V6B 5W3 604-6644123 Stephen.chuang@amecfw.com Abstract Shielding of substations from

More information

Uniform Hazard Spectrum(UHS) for performance based seismic design

Uniform Hazard Spectrum(UHS) for performance based seismic design Uniform Hazard Spectrum(UHS) for performance based seismic design *Jun-Kyoung Kim 1), Soung-Hoon Wee 2) and Seong-Hwa Yoo 2) 1) Department of Fire Protection and Disaster Prevention, Semyoung University,

More information

Fractional Factorial Designs

Fractional Factorial Designs Fractional Factorial Designs ST 516 Each replicate of a 2 k design requires 2 k runs. E.g. 64 runs for k = 6, or 1024 runs for k = 10. When this is infeasible, we use a fraction of the runs. As a result,

More information

Common Cause Failure Prediction Using Data Mapping

Common Cause Failure Prediction Using Data Mapping University of Richmond UR Scholarship Repository Math and Computer Science Faculty Publications Math and Computer Science 2002 Common Cause Failure Prediction Using Data Mapping Paul H. Kvam University

More information

Lecture 7: Karnaugh Map, Don t Cares

Lecture 7: Karnaugh Map, Don t Cares EE210: Switching Systems Lecture 7: Karnaugh Map, Don t Cares Prof. YingLi Tian Feb. 28, 2019 Department of Electrical Engineering The City College of New York The City University of New York (CUNY) 1

More information

Chapter 8. Calculation of PFD using FTA

Chapter 8. Calculation of PFD using FTA Chapter 8. Calculation of PFD using FTA Mary Ann Lundteigen Marvin Rausand RAMS Group Department of Mechanical and Industrial Engineering NTNU (Version 0.1) Lundteigen& Rausand Chapter 8.Calculation of

More information

Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants

Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants John Thomas With many thanks to Francisco Lemos for the nuclear expertise provided! System Studied: Generic

More information

Strange Combinatorial Connections. Tom Trotter

Strange Combinatorial Connections. Tom Trotter Strange Combinatorial Connections Tom Trotter Georgia Institute of Technology trotter@math.gatech.edu February 13, 2003 Proper Graph Colorings Definition. A proper r- coloring of a graph G is a map φ from

More information

WM2011 Conference, February 27 - March 3, 2011, Phoenix, AZ

WM2011 Conference, February 27 - March 3, 2011, Phoenix, AZ Methodology for Determination of Exposure Point Concentration Using both Systematic and Biased Samples for Radiological Risk and Dose Assessments 11488 Randy Hansen*, Michael Steven Passig*, Mahmudur Rahman**

More information

ATTACHMENT Mitigating Systems

ATTACHMENT Mitigating Systems ATTACHMENT 71111.01 INSPECTABLE AREA: Adverse Weather Protection CORNERSTONE: Initiating Events Mitigating Systems EFFECTIVE DATE: January 1, 2010 INSPECTION BASES: Weather conditions leading to loss of

More information

RELIABLITY OF CURVED TIMBER BEAM EXPOSED TO FIRE

RELIABLITY OF CURVED TIMBER BEAM EXPOSED TO FIRE Applications of Structural Fire Engineering, 15-16 October 2015, Dubrovnik, Croatia RELIABLITY OF CURVED TIMBER BEAM EXPOSED TO FIRE Robert Pečenko, Tomaž Hozjan, Goran Turk University of Ljubljana, Faculty

More information

Lectures 6. Lecture 6: Design Theory

Lectures 6. Lecture 6: Design Theory Lectures 6 Lecture 6: Design Theory Lecture 6 Announcements Solutions to PS1 are posted online. Grades coming soon! Project part 1 is out. Check your groups and let us know if you have any issues. We have

More information

Collecting reliability data and building of databases for PRA the PLG way

Collecting reliability data and building of databases for PRA the PLG way Collecting reliability data and building of databases for PRA the PLG way AESJ 09/05/18 Woody Epstein The Risk Alliance www.riskalliance.org info@riskalliance.org 1 USA Data Collection WASH 1400 NUREG/CR

More information

Revision of the AESJ Standard for Seismic Probabilistic Risk Assessment (2) Seismic Hazard Evaluation

Revision of the AESJ Standard for Seismic Probabilistic Risk Assessment (2) Seismic Hazard Evaluation Revision of the AESJ Standard for Seismic Probabilistic Risk Assessment (2) Seismic Hazard Evaluation Katsumi Ebisawa a, Katsuhiro Kamae b, Tadashi Annaka c, Hideaki Tsutsumi d And Atsushi Onouchi e a

More information

Chapter 2 Combinational Logic Circuits

Chapter 2 Combinational Logic Circuits Logic and Computer Design Fundamentals Chapter 2 Combinational Logic Circuits Part 2 Circuit Optimization Goal: To obtain the simplest implementation for a given function Optimization is a more formal

More information

Effect of Correlations of Component Failures and Cross-connections of EDGs on Seismically Induced Core Damage of a Multi-unit Site

Effect of Correlations of Component Failures and Cross-connections of EDGs on Seismically Induced Core Damage of a Multi-unit Site Nov. 14, 2007 Effect of Correlations of Component Failures and Cross-connections of EDGs on Seismically Induced Core Damage of a Multi-unit Site Ken MURAMATSU*, Qiao LIU(presenter)*, Tomoaki UCHIYAMA**

More information

Multilevel Logic Synthesis Algebraic Methods

Multilevel Logic Synthesis Algebraic Methods Multilevel Logic Synthesis Algebraic Methods Logic Circuits Design Seminars WS2010/2011, Lecture 6 Ing. Petr Fišer, Ph.D. Department of Digital Design Faculty of Information Technology Czech Technical

More information

LOCAL FUSION OF AN ENSEMBLE OF SEMI-SUPERVISED SELF ORGANIZING MAPS FOR POST-PROCESSING ACCIDENTAL SCENARIOS

LOCAL FUSION OF AN ENSEMBLE OF SEMI-SUPERVISED SELF ORGANIZING MAPS FOR POST-PROCESSING ACCIDENTAL SCENARIOS LOCAL FUSION OF AN ENSEMBLE OF SEMI-SUPERVISED SELF ORGANIZING MAPS FOR POST-PROCESSING ACCIDENTAL SCENARIOS Francesco Di Maio 1, Roberta Rossetti 1, Enrico Zio 1,2 1 Energy Department, Politecnico di

More information

Reliability of Safety-Critical Systems Chapter 8. Probability of Failure on Demand using fault trees

Reliability of Safety-Critical Systems Chapter 8. Probability of Failure on Demand using fault trees Reliability of Safety-Critical Systems Chapter 8. Probability of Failure on Demand using fault trees Mary Ann Lundteigen and Marvin Rausand mary.a.lundteigen@ntnu.no &marvin.rausand@ntnu.no RAMS Group

More information

SAFETY MARGIN SENSITIVITY ANALYSIS FOR MODEL SELECTION IN NUCLEAR POWER PLANT PROBABILISTIC SAFETY ASSESSMENT ABSTRACT

SAFETY MARGIN SENSITIVITY ANALYSIS FOR MODEL SELECTION IN NUCLEAR POWER PLANT PROBABILISTIC SAFETY ASSESSMENT ABSTRACT SAFETY MARGIN SENSITIVITY ANALYSIS FOR MODEL SELECTION IN NUCLEAR POWER PLANT PROBABILISTIC SAFETY ASSESSMENT Francesco Di Maio 1, Claudia Picoco 1, Enrico Zio 1,2, Valentin Rychkov 3 1 Energy Department,

More information

PARAMETRIC STUDY OF THE STRUCTURAL CAPACITY OF REINFORCED CONCRETE CONTAINMENT SUBJECTED TO LARGE COMMERICAL AIRCRFAT IMPACT

PARAMETRIC STUDY OF THE STRUCTURAL CAPACITY OF REINFORCED CONCRETE CONTAINMENT SUBJECTED TO LARGE COMMERICAL AIRCRFAT IMPACT Transactions, SMiRT-23, Paper 285 PARAMETRIC STUDY OF THE STRUCTURAL CAPACITY OF REINFORCED CONCRETE CONTAINMENT SUBJECTED TO LARGE COMMERICAL AIRCRFAT IMPACT Marin Kostov 1, Milko Miloshev 2, Zhivko Nikolov

More information

Exercises, II part Exercises, II part

Exercises, II part Exercises, II part Inference: 12 Jul 2012 Consider the following Joint Probability Table for the three binary random variables A, B, C. Compute the following queries: 1 P(C A=T,B=T) 2 P(C A=T) P(A, B, C) A B C 0.108 T T

More information

VERIFICATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL CHANNELS OF THE TRIGA MARK II REACTOR, LJUBLJANA

VERIFICATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL CHANNELS OF THE TRIGA MARK II REACTOR, LJUBLJANA International Conference Nuclear Energy for New Europe 2002 Kranjska Gora, Slovenia, September 9-12, 2002 www.drustvo-js.si/gora2002 VERIFATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL

More information

Gate-Level Minimization

Gate-Level Minimization Gate-Level Minimization Dr. Bassem A. Abdullah Computer and Systems Department Lectures Prepared by Dr.Mona Safar, Edited and Lectured by Dr.Bassem A. Abdullah Outline 1. The Map Method 2. Four-variable

More information

Suppose we needed four batches of formaldehyde, and coulddoonly4runsperbatch. Thisisthena2 4 factorial in 2 2 blocks.

Suppose we needed four batches of formaldehyde, and coulddoonly4runsperbatch. Thisisthena2 4 factorial in 2 2 blocks. 58 2. 2 factorials in 2 blocks Suppose we needed four batches of formaldehyde, and coulddoonly4runsperbatch. Thisisthena2 4 factorial in 2 2 blocks. Some more algebra: If two effects are confounded with

More information

Integrated Dynamic Decision Analysis: a method for PSA in dynamic process system

Integrated Dynamic Decision Analysis: a method for PSA in dynamic process system Integrated Dynamic Decision Analysis: a method for PSA in dynamic process system M. Demichela & N. Piccinini Centro Studi su Sicurezza Affidabilità e Rischi, Dipartimento di Scienza dei Materiali e Ingegneria

More information

Probabilistic Risk Assessment

Probabilistic Risk Assessment r Chapter 5 5.1 Introduction 5-1 5.1.1 Chapter Content This chapter presents a methodology for event analysis. DBAs, as discussed in the previous chapter, define the events to be analyzed for PSAs. Risk

More information

Apportioning Transient Combustible Fire Frequency via Areal Factors: More Complicated Than It May Seem

Apportioning Transient Combustible Fire Frequency via Areal Factors: More Complicated Than It May Seem Apportioning Transient Combustible Fire Frequency via Areal Factors: More Complicated Than It May Seem Raymond H.V. Gallucci, Ph.D., P.E. U.S. Nuclear Regulatory Commission (USNRC), MS O-10C15, Washington,

More information

DIGITAL ELECTRONICS & it0203 Semester 3

DIGITAL ELECTRONICS & it0203 Semester 3 DIGITAL ELECTRONICS & it0203 Semester 3 P.Rajasekar & C.M.T.Karthigeyan Asst.Professor SRM University, Kattankulathur School of Computing, Department of IT 8/22/2011 1 Disclaimer The contents of the slides

More information