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Safety, Reliability, Human Factors, and Human Error in Nuclear Power Plants [Kõva köide]

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(University of Ottawa, Canada.)
  • Formaat: Hardback, 272 pages, kõrgus x laius: 234x156 mm, kaal: 521 g, 34 Illustrations, black and white
  • Ilmumisaeg: 15-Dec-2017
  • Kirjastus: CRC Press
  • ISBN-10: 1138080993
  • ISBN-13: 9781138080997
Teised raamatud teemal:
Safety, Reliability, Human Factors, and Human Error in Nuclear Power PlantsSuurem pilt
  • Formaat: Hardback, 272 pages, kõrgus x laius: 234x156 mm, kaal: 521 g, 34 Illustrations, black and white
  • Ilmumisaeg: 15-Dec-2017
  • Kirjastus: CRC Press
  • ISBN-10: 1138080993
  • ISBN-13: 9781138080997
Teised raamatud teemal:
Püsilink: https://www.kriso.ee/db/9781138080997.html
Märksõnad:

Each year billions of dollars are being spent in the area of nuclear power generation to design, construct, manufacture, operate, and maintain various types of systems around the globe. Many times these systems fail due to safety, reliability, human factors, and human error related problems. The main objective of this book is to combine nuclear power plant safety, reliability, human factors, and human error into a single volume for those individuals that work closely during the nuclear power plant design phase, as well as other phases, thus eliminating the need to consult many different and diverse sources in obtaining the desired information.

Preface xv
Author xix
1 Introduction 1(14)
1.1 Background
1(1)
1.2 Safety, Reliability, Human Factors, and Human Error-Related Facts, Figures, and Examples
1(2)
1.3 Terms and Definitions
3(1)
1.4 Useful Information on Safety, Reliability, Human Factors, and Human Error in Nuclear Power Plants
4(6)
1.4.1 Books
5(1)
1.4.2 Journals
6(1)
1.4.3 Conference Proceedings
7(1)
1.4.4 Technical Reports
8(1)
1.4.5 Data Sources
9(1)
1.4.6 Organizations
9(1)
1.5 Scope of the Book
10(1)
1.6 Problems
11(1)
References
12(3)
2 Basic Mathematical Concepts 15(18)
2.1 Introduction
15(1)
2.2 Arithmetic Mean and Mean Deviation
15(2)
2.2.1 Arithmetic Mean
16(1)
2.2.2 Mean Deviation
16(1)
2.3 Boolean Algebra Laws
17(1)
2.4 Probability Definition and Properties
18(2)
2.5 Useful Mathematical Definitions
20(4)
2.5.1 Definition I: Cumulative Distribution Function
20(1)
2.5.2 Definition II: Probability Density Function
21(1)
2.5.3 Definition III: Expected Value
21(1)
2.5.4 Definition IV: Laplace Transform
22(1)
2.5.5 Definition V: Final Value Theorem Laplace Transform
23(1)
2.6 Probability Distributions
24(4)
2.6.1 Binomial Distribution
24(1)
2.6.2 Exponential Distribution
25(1)
2.6.3 Rayleigh Distribution
26(1)
2.6.4 Weibull Distribution
27(1)
2.6.5 Bathtub Hazard Rate Curve Distribution
27(1)
2.7 Solving First-Order Differential Equations Using Laplace Transforms
28(2)
2.8 Problems
30(1)
References
30(3)
3 Safety, Reliability, Human Factors, and Human Error Basics 33(30)
3.1 Introduction
33(1)
3.2 Safety Management Principles and Safety and Engineers
34(1)
3.3 Accident Causation Theories
35(3)
3.3.1 The Domino Theory
35(2)
3.3.2 The Human Factors Theory
37(1)
3.4 Bathtub Hazard Rate Curve
38(2)
3.5 General Reliability Formulas
40(3)
3.5.1 Failure (or Probability) Density Function
40(1)
3.5.2 Hazard Rate (Time-Dependent Failure Rate) Function
40(1)
3.5.3 General Reliability Function
41(1)
3.5.4 Mean Time to Failure
42(1)
3.6 Reliability Networks
43(10)
3.6.1 Series Network
43(3)
3.6.2 Parallel Network
46(2)
3.6.3 k-out-of-n Network
48(2)
3.6.4 Standby System
50(2)
3.6.5 Bridge Network
52(1)
3.7 Human Factor Objectives and Typical Human Behaviors
53(1)
3.8 Human Sensory Capacities
54(1)
3.9 Useful Human Factor-Related Guidelines
55(1)
3.10 Useful Mathematical Human Factor-Related Formulas
56(2)
3.10.1 Formula I: Inspector Performance
56(1)
3.10.2 Formula II: Character Height
57(1)
3.10.3 Formula III: Rest Period
57(1)
3.10.4 Formula IV: Glare Constant
58(1)
3.11 Reasons for Human Error Occurrence and Types of Human Errors
58(2)
3.12 Problems
60(1)
References
61(2)
4 Methods for Performing Safety, Reliability, Human Factors, and Human Error Analysis in Nuclear Power Plants 63(26)
4.1 Introduction
63(1)
4.2 Technique of Operations Review (TOR)
64(1)
4.3 Root Cause Analysis (RCA)
65(1)
4.4 Interface Safety Analysis (ISA)
66(1)
4.5 Task Analysis
67(1)
4.6 Hazards and Operability Analysis (HAZOP)
68(1)
4.7 Pontecorvo Method
69(2)
4.8 Failure Modes and Effect Analysis (FMEA)
71(1)
4.9 Man-Machine Systems Analysis
72(1)
4.10 Maintenance Personnel Performance Simulation (MAPPS) Model
73(1)
4.11 Fault Tree Analysis (FTA)
74(5)
4.11.1 Fault Tree Probability Evaluation
76(2)
4.11.2 FTA Benefits and Drawbacks
78(1)
4.12 Markov Method
79(3)
4.13 Probability Tree Method
82(2)
4.14 Problems
84(1)
References
85(4)
5 Human Reliability Analysis Methods for Nuclear Power Stations 89(16)
5.1 Introduction
89(1)
5.2 Incorporation of the HRA Integrally into a Probabilistic Risk Assessment (PRA) and Human Reliability Method Requirements
89(2)
5.3 HRA Process Steps and Their End Results
91(1)
5.4 HRA Methods
91(11)
5.4.1 Success Likelihood Index Method-Multiattribute Utility Decomposition (SLIM-MAUD)
93(1)
5.4.2 Technique for Human Error Rate Prediction (THERP)
94(1)
5.4.3 Accident Sequence Evaluation Program (ASEP)
95(1)
5.4.4 A Technique for Human Event Analysis (ATHEANA)
95(2)
5.4.5 Human Error Assessment and Reduction Technique (HEART)
97(1)
5.4.6 Cognitive Reliability and Error Analysis Method (CREAM)
98(2)
5.4.7 Standardized Plant Analysis Risk-Human Reliability Analysis (SPAR-HRA)
100(2)
5.5 Problems
102(1)
References
102(3)
6 Safety in Nuclear Power Plants 105(18)
6.1 Introduction
105(1)
6.2 Nuclear Power Plant Safety Objectives
105(1)
6.3 Nuclear Power Plant Fundamental Safety Principles
106(2)
6.3.1 Management Responsibilities
106(1)
6.3.2 Strategy of Defense in Depth
107(1)
6.3.3 General Technical Principles
107(1)
6.4 Nuclear Power Plant Specific Safety Principles
108(5)
6.4.1 Siting
109(1)
6.4.2 Design
109(1)
6.4.3 Manufacturing and Construction
110(1)
6.4.4 Commissioning
110(1)
6.4.5 Operation
111(1)
6.4.6 Accident Management
112(1)
6.4.7 Decommissioning
112(1)
6.4.8 Emergency Preparedness
113(1)
6.5 Management of Safety in Nuclear Power Plant Design
113(1)
6.6 Safety-Related Requirements in the Design of Specific Nuclear Plant Systems
114(3)
6.7 Deterministic Safety Analysis for Nuclear Power Plants
117(1)
6.7.1 Deterministic Safety Analysis Application Areas
117(1)
6.8 Nuclear Power Plant Safety-Related Documents and Standards
118(2)
6.9 Problems
120(1)
References
121(2)
7 Nuclear Power Plant Accidents 123(12)
7.1 Introduction
123(1)
7.2 The International Nuclear Event Scale (INES)
123(1)
7.3 World Nuclear Power Plant Accidents' Fatalities, Rankings, and Costs
124(3)
7.4 Three Mile Island Accident
127(1)
7.4.1 Radiological Health Effects
128(1)
7.4.2 The Three Mile Island Reactor No. 2 Cleanup
128(1)
7.4.3 The Accident's Effect on the Nuclear Power Industry
128(1)
7.5 The Chernobyl Accident
128(1)
7.5.1 Dispersion and Disposition of Radionuclides
129(1)
7.5.2 Operator Error
129(1)
7.6 The Fukushima Accident
129(1)
7.7 Lessons Learned from the Three Mile Island, Chernobyl, and Fukushima Accidents
130(1)
7.8 Comparison of the Chernobyl and Three Mile Island Accidents and of the Fukushima and Chernobyl Accidents
131(1)
7.9 Problems
132(1)
References
133(2)
8 Reliability and Maintenance Programs for Nuclear Power Plants 135(16)
8.1 Introduction
135(1)
8.2 A Reliability Program's Objectives and Requirements
135(2)
8.3 Guidance for Developing Reliability Programs
137(4)
8.3.1 Using Systematic Approaches for Identifying and Ranking SIS
138(1)
8.3.2 Specifying Reliability-Related Targets
138(1)
8.3.3 Highlighting and Describing Potential Failure Modes
139(1)
8.3.4 Stating Minimum Capabilities and Levels of Performance
139(1)
8.3.5 Maintenance Program
139(1)
8.3.6 Inspections, Tests, Modeling, and Monitoring
140(1)
8.3.6.1 Providing for Inspections and Tests
140(1)
8.3.6.2 Modeling
140(1)
8.3.6.3 Monitoring Performance and Reliability
140(1)
8.3.7 Implementing a Reliability Program
140(1)
8.3.8 Recording and Reporting Results of Reliability Program-Related Activities
140(1)
8.3.9 Documenting a Reliability Program
140(1)
8.4 A Maintenance Program's Objectives, Scope, and Background
141(1)
8.5 Guidance for Developing Maintenance Programs
141(7)
8.5.1 Program Basis
141(2)
8.5.2 Maintenance Organization
143(1)
8.5.3 Maintenance Activities
144(1)
8.5.4 Structure, System, or Component Monitoring
145(1)
8.5.5 Maintenance Work
146(1)
8.5.6 Spare Parts and Procurement
147(1)
8.5.7 Management Assessment and Program Review
147(1)
8.5.8 Record Keeping
148(1)
8.6 Reliability and Maintenance Program-Related Standards
148(1)
8.7 Problems
149(1)
References
150(1)
9 Human Factors and Human Error in Nuclear Power Generation 151(12)
9.1 Introduction
151(1)
9.2 Aging Nuclear Power Plant Human Factor-Related Issues
151(1)
9.3 Human Factor-Related Issues That Can Have a Positive Impact on the Decommissioning of Nuclear Power Plants
152(2)
9.3.1 Maintaining a Safety Culture
152(1)
9.3.2 Uncertainty about the Future
153(1)
9.3.3 Retaining Organizational Memory
153(1)
9.3.4 Maintaining Adequate Competence for Decommissioning
154(1)
9.4 Human Factors Engineering Design Goals with Regard to Nuclear Power Generation Systems and Responsibilities
154(1)
9.5 Human Factors Review Guide for Next-Generation Nuclear Reactors
155(3)
9.6 Human Error Facts, Figures, and Examples Concerning Nuclear Power Generation
158(1)
9.7 Occurrences Caused by Operator Errors during Operation in Commercial Nuclear Power Plants
159(1)
9.8 Causes of Operator Errors in Commercial Nuclear Power Plant Operations
160(1)
9.9 Problems
160(1)
References
161(2)
10 Human Factors and Human Error in Nuclear Power Plant Maintenance 163(18)
10.1 Introduction
163(1)
10.2 Study of Human Factors in Power Plant Maintenance
163(1)
10.3 Elements Relating to Human Performance That Can Contribute to an Effective Maintenance Program in Nuclear Power Plants
164(1)
10.4 Useful Human Factors Methods to Assess and Improve Nuclear Power Plant Maintainability
165(2)
10.4.1 Structured Interviews
165(1)
10.4.2 Task Analysis
166(1)
10.4.3 Surveys
166(1)
10.4.4 Potential Accident/Damage Analysis
166(1)
10.4.5 Critical Incident Technique
167(1)
10.5 Nuclear Power Plant Maintenance Error-Related Facts, Figures, and Examples
167(1)
10.6 Causes of Human Error in Nuclear Power Plant Maintenance and Maintenance Tasks Most Susceptible to Human Error in Nuclear Power Plants
168(1)
10.7 Digital Plant Protection Systems Maintenance Task-Related Human Errors
169(1)
10.8 Useful Guidelines for Human Error Reduction and Prevention in Nuclear Power Plant Maintenance
170(1)
10.9 Methods for Performing Maintenance Error Analysis in Nuclear Power Plants
171(6)
10.9.1 Markov Method
171(3)
10.9.2 Fault Tree Analysis
174(2)
10.9.3 Maintenance Personnel Performance Simulation (MAPPS) Model
176(1)
10.10 Problems
177(1)
References
178(3)
11 Human Factors in Nuclear Power Plant Control Systems 181(12)
11.1 Introduction
181(1)
11.2 Human Performance-Related Advanced Control Room Technology Issues and Control Room Design-Related Deficiencies That Can Lead to Human Error
181(2)
11.3 Human Engineering Discrepancies in Control Room Visual Displays
183(1)
11.4 Human Factor-Related Evaluation of Control Room Annunciators
184(2)
11.5 Benefits of Considering Human Factors in Digital Control Room Upgrades and an Approach for Incorporating Human Factor Considerations in Digital Control Room Upgrades
186(1)
11.6 Recommendations for Overcoming Problems When Digital Control Room Upgrades Are Undertaken without Considering Human Factors into the Design
187(3)
11.7 Problems
190(1)
References
190(3)
12 Mathematical Models for Performing Safety, Reliability, and Human Error Analysis in Nuclear Power Plants 193(26)
12.1 Introduction
193(1)
12.2 Model I
193(4)
12.3 Model II
197(2)
12.4 Model III
199(2)
12.5 Model IV
201(3)
12.6 Model V
204(3)
12.7 Model VI
207(4)
12.8 Model VII
211(2)
12.9 Model VIII
213(3)
12.10 Problems
216(1)
References
217(2)
Appendix: Bibliography 219(22)
Index 241
Dr. B.S. Dhillon is a professor of Engineering Management in the Department of Mechanical Engineering at the University of Ottawa. He has served as a Chairman/Director of Mechanical Engineering Department/Engineering Management Program for over 10 years at the same institution. He is the founder of the probability distribution named Dhillon Distribution/Law/Model by statistical researchers in their publications around the world. He has published over 389 {(i.e., 234( 70 single authored + 164 co-authored) journal and 155 conference proceedings} articles on reliability engineering, maintainability, safety, engineering management, etc. He is or has been on the editorial boards of 12 international scientific journals. In addition, Dr. Dhillon has written 45 books on various aspects of health care, engineering management, design, reliability, safety, and quality published by Wiley (1981), Van Nostrand (1982), Butterworth (1983), Marcel Dekker (1984), Pergamon (1986), etc. His books are being used in over 100 countries and many of them are translated into languages such as German, Russian, Chinese, and Persian (Iranian).

He has served as General Chairman of two international conferences on reliability and quality control held in Los Angeles and Paris in 1987. Prof. Dhillon has also served as a consultant to various organizations and bodies and has many years of experience in the industrial sector. He has lectured in over 50 countries, including keynote addresses at various international scientific conferences held in North America, Europe, Asia, and Africa. In March 2004, Dr. Dhillon was a distinguished speaker at the Conf./Workshop on Surgical Errors (sponsored by White House Health and Safety Committee and Pentagon), held at the Capitol Hill (One Constitution Avenue, Washington, D.C.).

Professor Dhillon attended the University of Wales where he received a BS in electrical and electronic engineering and an MS in mechanical engineering. He received a Ph.D. in industrial engineering from the University of Windsor.