Nuclear power and engineering Books

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Book SynopsisDetailing the estimation and perception of nuclear risk, this book follows military and civilian nuclear accidents, plus the systems put in place by national and international authorities for recording and analyzing feedback. Prevention and anticipation being the best defenses against a nuclear accident, the authorities have also categorized the different types of accidents, and are doing research to better understand and control them. In light of this, this book shows how the authorities take practical measures to protect neighboring populations and limit radioactive contamination of the environment. France�s experience in this arena is well-documented and a chapter of this book is devoted to the fight against terrorist attacks in the nuclear field. Nuclear Accidents is based on scientifically-recognized publications, as well as on reports from the various countries concerned, and the national and international organizations competent in this field (IAEA, WHO, UNSCEAR, IRSN, etc.).Table of ContentsAcknowledgments xi Preface xiii Chapter 1. Assessment and Perception of Nuclear Risk 1 1.1. Introduction 1 1.2. Danger, exposure, radiotoxicity and risk 4 1.2.1. Identification of radionuclide hazards 5 1.2.2. Contamination of the environment, including the anthroposphere, by radionuclides 7 1.2.3. Exposure to radiation 11 1.2.4. Collective doses 17 1.3. From dose to adverse effect in non-human organisms (flora and fauna) 17 1.3.1. The harmful effects of ionizing radiation 18 1.3.2. The dose–response relationship 20 1.3.3. Recommended threshold values 22 1.4. From dose to adverse effect in humans 24 1.4.1. Deterministic and stochastic effects 24 1.4.2. Dose–response relationships for average doses: epidemiological studies 25 1.4.3. Responses to low doses 26 1.5. Radiation protection and recommendations for human irradiation 32 1.6. Risk perception 35 1.6.1. Probability of a future nuclear accident 36 1.6.2. Countries using or renouncing the use of nuclear energy 37 1.6.3. Opinion polls on nuclear power 38 1.6.4. Estimated risk and perceived risk 41 1.7. Conclusion 42 Chapter 2. Lessons from the Past in the Field of Nuclear Accidents 45 2.1. Early signals and late lessons 45 2.2. Structures for disseminating information on radioactive risk 45 2.2.1. Situation from 1945 to 1990 46 2.2.2. Situation from the Chernobyl accident to the present day 47 2.2.3. The example of France 48 2.2.4. Future change? 50 2.3. Feedback (REX) 51 2.3.1. Introduction: what is REX? 51 2.3.2. The overall REX process 52 2.3.3. Causes of REX failure 54 2.4. Lessons from the past 55 2.4.1. Lessons learned from military nuclear activities and accidents 55 2.4.2. Lessons from industrial accidents 57 2.4.3. Medical accidents 72 2.5. Crisis exercises 77 2.5.1. Transnational exercises 77 2.5.2. National exercises 78 2.6. Incident and accident reporting 80 2.6.1. A common severity scale 80 2.6.2. Management of declarations 81 2.6.3. Reporting systems 81 2.6.4. Websites 82 2.7. Conclusion 83 Chapter 3. Research for the Future 85 3.1. Introduction: safety and the main types of accidents 85 3.1.1. Safety history 85 3.1.2. The main safety objectives 86 3.1.3. Defense in depth 87 3.1.4. New research in the field of nuclear safety 88 3.1.5. The aging of nuclear installations 90 3.2. International actions 92 3.2.1. Improving the organization of security at the level of each state 92 3.2.2. The IAEA 94 3.2.3. The NEA 95 3.2.4. The ICRP 98 3.2.5. UNSCEAR 99 3.2.6. The ICRU 100 3.2.7. The IRSN at international level 100 3.3. European actions 101 3.3.1. Euratom 101 3.3.2. Complementary safety assessments (ECS) process 102 3.4. French actions 103 3.5. Advances in nuclear safety 106 3.5.1. Better knowledge of nuclear fuel 107 3.5.2. Better preventing the risk of steam and hydrogen explosions 110 3.5.3. Controlling radionuclide releases 111 3.5.4. Consequences of a fire 112 3.5.5. Knowing more about corium 113 3.5.6. Controlling a water injection into a molten core 115 3.5.7. Mastering electrical distribution systems 115 3.5.8. Improving modeling 116 3.6. Advances in radioecology 118 3.6.1. Determination of the source term 118 3.6.2. Modeling of radionuclide dispersion in the terrestrial environment 119 3.6.3. Modeling of radionuclide dispersion in aquatic environments 120 3.6.4. Modeling of trophic transfer of radionuclides in organisms 121 3.7. Advances in radiation protection 121 3.7.1. Improving the radiological protection system 122 3.7.2. Improving the management of a nuclear accident 125 3.8. Safety research in other types of nuclear installations 128 3.8.1. Cooling pools 128 3.8.2. Spent fuel reprocessing plants 129 3.8.3. Sodium-cooled fast neutron reactors 129 3.8.4. ITER (International Thermonuclear Experimental Reactor) fusion facility 129 3.8.5. Better understanding of criticality 130 3.9. Advances in the humanities and social sciences 130 3.10. Conclusion 131 Chapter 4. Management of the Emergency Phase of a Nuclear Accident 133 4.1. Introduction 133 4.2. The first actions of the threat and rejection periods 134 4.2.1. Radioactive releases in the event of an accident from a nuclear reactor 135 4.2.2. Radioactivity measurements during a nuclear accident 136 4.3. Population management in the emergency phase 138 4.3.1. Containment or sheltering of the population 140 4.3.2. Mass evacuation or evacuation of part of the population 141 4.3.3. Distribution of stable iodine tablets 152 4.4. Food supply management 156 4.4.1. Recommended values 156 4.4.2. Regulatory values 158 4.5. Intervention levels for the protection of populations 160 4.5.1. International recommendations 160 4.5.2. The texts of the various states 163 4.6. The organization of crisis management in France 164 4.6.1. Documentation of the ORSEC plan 165 4.6.2. The subdivisions of the ORSEC plan 167 4.6.3. French actors in nuclear crisis management 167 4.6.4. The internal emergency plan 168 4.6.5. The plan particulier d’intervention (PPI, special intervention plans) 170 4.6.6. Other complementary plans of the PPI 180 4.7. Exiting the emergency phase 182 4.8. Conclusion 183 Chapter 5. Management of the Post-accident Phase 185 5.1. Introduction 185 5.2. The actions to be taken 186 5.2.1. Priority actions to be undertaken 187 5.2.2. Actions during the transitional period 188 5.2.3. Long-term actions 189 5.2.4. Radioactivity measurements following a nuclear accident 190 5.3. Environmental management 191 5.3.1. Management of aquatic environments 191 5.3.2. Management of terrestrial environments 193 5.4. Managing the anthroposphere 195 5.4.1. Decontamination of living areas 196 5.4.2. Nuclear waste management 196 5.4.3. Agricultural management 197 5.4.4. Managing the economy 202 5.4.5. Food supply management 203 5.5. Management of exposed populations 204 5.5.1. Limiting people’s exposure to radiation 204 5.5.2. Radiological monitoring of exposed populations 206 5.5.3. Radiological and health monitoring of nuclear workers 208 5.5.4. Health monitoring of exposed populations 208 5.5.5. The return of evacuated populations 209 5.5.6. The experience of local populations in contaminated environments 211 5.5.7. Human dignity 211 5.6. The organization of post-accident management 212 5.6.1. International and European recommendations 212 5.6.2. French doctrine 215 5.7. Conclusion 221 Chapter 6. Terrorist Attacks and Nuclear Security 223 6.1. Introduction 223 6.2. Malicious acts 224 6.2.1. Attempts at radiation aggression 225 6.2.2. The assassination of Alexander Litvinenko 225 6.2.3. Arafat’s death 226 6.2.4. Overflights and intrusions into nuclear facilities 228 6.3. Possible terrorist attacks 228 6.3.1. The use of a nuclear weapon 229 6.3.2. The use of a “dirty” bomb 229 6.3.3. Attack on a nuclear installation or transport 231 6.3.4. The release of radioactive material 231 6.3.5. Cyber-attacks 232 6.4. The consequences of a terrorist act in the nuclear field 233 6.4.1. The health consequences 234 6.4.2. The psychological consequences 236 6.4.3. Countermeasures in the event of terrorist attacks 237 6.5. Organizational preparation for a terrorist threat 240 6.6. Prevention of terrorist risk in the nuclear field 242 6.6.1. Nuclear non-proliferation 242 6.6.2. Trafficking in military weapons and radionuclides 245 6.6.3. The actions to be taken 247 6.6.4. The limitation of nuclear materials 248 6.7. Conclusion 249 Chapter 7. General Conclusions 253 7.1. The probability of military and civil accidents 253 7.1.1. Nuclear risks and probabilities 253 7.1.2. The causes of accidents 254 7.2. The environmental consequences of accidents 255 7.3. The health consequences of accidents 256 7.4. The economic consequences of accidents 260 7.5. Prevention of nuclear accidents 262 7.6. Management of the emergency and post-accident phases 264 7.7. Perception of nuclear risk 264 7.8. Public information 265 References 269 Acronyms and Abbreviations 339 Index 355

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Book SynopsisSince the 1970s, the field of industrial reliability has evolved significantly, in part due to the design and early operation of the first generation nuclear power plants. Indeed, the needs of this sector have led to the development of specific and innovative reliability methods, which have since been taken up and adapted by other industrial sectors, leading to the development of the management of uncertainties and Health and Usage Monitoring Systems. In this industry, reliability assessment approaches have matured. There are now methods, data and tools available that can be used with confidence for many industrial applications. The purpose of this book is to present and illustrate them with real study cases.The book addresses the evolution of reliability methods, experience feedback and expertise (as data is essential for estimating reliability), the reliability of socio-technical systems and probabilistic safety assessments, the structural reliability and probabilistic models in mechanics, the reliability of equipment and the impact of maintenance on their behavior, human and organizational factors and the impact of big data on reliability. Finally, some R&D perspectives that can be developed in the future are presented. Written by several engineers, statisticians and human and organizational factors specialists in the nuclear sector, this book is intended for all those who are faced with a reliability assessment of their installations or equipment: decision-makers, engineers, designers, operation or maintenance engineers, project managers, human and organizational factors specialists, experts and regulatory authority inspectors, teachers, researchers and doctoral students.Table of ContentsForeword by Philippe Le Poac xi Foreword by Antoine Grall xvii Preface xxi André Lannoy Acknowledgments xxiii André Lannoy Author Biographies xxv Chapter 1 Aims and Introduction 1 André Lannoy 1.1 The aims of this work 1 1.2 Reliability, an application of probability theory 2 1.2.1 What is reliability? 2 1.2.2 The early days of reliability 3 1.2.3 The birth of modern reliability 5 1.2.4 The development of modern reliability 1948–1960 5 1.2.5 The advent of reliability specialists 1960–1974 6 1.2.6 The “safety culture decade” 1975–1990 7 1.2.7 Maximizing efficiency, performances and profits 1990–2007 8 1.2.8 The return to safety, risk aversion 2007–2020 9 1.3 Generating nuclear power 10 1.4 Presentation of the book’s content 15 1.5 References 17 Chapter 2 Input Data: Operation Feedback and Expertise 21 André Lannoy and Emmanuel Remy 2.1 The purposes of operation feedback 21 2.2 What is operation feedback? 23 2.3 The operation feedback approach 25 2.4 “Event” operation feedback 28 2.5 “Equipment” operation feedback 29 2.5.1 The maintenance model: an approach according to function 29 2.5.2 Failure analysis 31 2.5.3 Failure criteria 33 2.5.4 Data quality 33 2.6 Reliability analysis 35 2.6.1 The components studied 35 2.6.2 Data characteristics 36 2.6.3 Principles of simple reliability data estimation for PSAs 38 2.7 Conclusion 39 2.8 References 41 Chapter 3 The Principles of Calculating Reliability in Level 1 PSAs 43 Marc Bouissou 3.1 Introduction 43 3.2 The basis of all calculations: an exponential approximation 45 3.2.1 The principle of exponential approximations 45 3.2.2 NRI exponential approximation 46 3.3 The models used 48 3.3.1 Event trees 48 3.3.2 Fault trees 51 3.4 Quantification of PSAs 54 3.4.1 Calculating the probability of UCs that are conditional on an initiator 55 3.4.2 Calculating importance factors 57 3.4.3 The uncertainty calculation 59 3.5 The question of the level of detail 60 3.6 Practical problems: model size, high probabilities 62 3.6.1 Model size and combinatorial explosion 63 3.6.2 Fire, flood and earthquake PSAs: the problem of high probabilities 64 3.7 “Cousin” models of PSA models 65 3.7.1 Event sequence diagrams 65 3.7.2 Bow tie diagram 66 3.7.3 Boolean logic-driven Markov processes 66 3.8 How can we improve the precision of classic PSAs? 70 3.8.1 Principles of the I&AB method 70 3.8.2 What gains does I&AB allow? 71 3.8.3 Numerical application of I&AB 72 3.9 A line of research: “dynamic PSAs” 75 3.10 Software for carrying out PSAs 76 3.11 References 78 Chapter 4 Structural Reliability: General Presentation, Applications for Nuclear Power Plants 83 Emmanuel Ardillon 4.1 General presentation of SRA 83 4.1.1 Why SRA? 83 4.1.2 What does SRA consist of? 86 4.1.3 Old foundations but a recent history 87 4.1.4 SRA: from the R-S elementary case (resistance-stress method) to the general case 88 4.1.5 A brief overview of calculation methods 90 4.1.6 OpenTURNS: the processing tool for uncertainty quantifications co-developed and used at EDF 95 4.2 Structural reliability in the nuclear power generation industry 97 4.2.1 Optimizing the maintenance policy for steam generators 98 4.2.2 Risk of fast fracture of PWR reactor pressure vessels 98 4.3 The pressurizer, an example of an exploratory exercise in the application of probabilistic approaches 100 4.4 Probabilistic optimization of the maintenance of nuclear power plant steel components 102 4.4.1 Introduction 102 4.4.2 Specifying the problem (stage A) 103 4.4.3 Uncertainty quantification (stage B) 105 4.4.4 Uncertainty propagation: calculating the overall risk of thinning points (stage C) 106 4.4.5 Using probabilistic results: determining points to repair 107 4.4.6 Conclusion and perspectives on this application 108 4.5 Structural reliability for hydroelectricity – the reliability of penstocks: evaluation of calculation values for mechanical strength diagnostics 110 4.6 Conclusion 112 4.7 References 113 Chapter 5 Probabilistic and Statistical Modeling for the Reliability of Industrial Equipment 117 Emmanuel Remy 5.1 Introduction 117 5.2 Some general preliminary remarks 118 5.3 Nonparametric approaches 124 5.4 Parametric models 126 5.4.1 Introduction 126 5.4.2 Some models adapted to non-repairable components 127 5.4.3 Taking account of influencing factors 132 5.4.4 Imperfect maintenance models for repairable equipment 135 5.4.5 Stochastic degradation models 140 5.5 Frequentist inference 147 5.6 Bayesian statistics 153 5.7 Model validation and selection 157 5.8 Case study for illustration 160 5.9 Openings and prospects for R&D 163 5.10 Software tools 164 5.11 References 164 Chapter 6 The Human and Organizational Dimensions of Reliability and Nuclear Safety 171 Nicolas Dechy, Yves Dien And Jean-François Vautier 6.1 Introduction and historical context in the nuclear field 171 6.2 Definition of the human and organizational dimensions of dependability and nuclear safety 173 6.3 Theories on accidents and reliability 175 6.4 Human and social sciences methods for collecting and analyzing data 181 6.5 Making human activities reliable 183 6.5.1 “Human error”: man is a fallible reliability agent 183 6.5.2 Training 185 6.5.3 Applying the procedure or demonstrating skills? 187 6.5.4 Analyzing real activity and work situations 188 6.5.5 Man–machine interfaces: the case of control rooms 189 6.5.6 Consideration of HOFs during design and modifications 190 6.5.7 Operation actions and their feasibility 191 6.5.8 Quantitative approach to human reliability 192 6.5.9 HF in maintenance interventions 193 6.6 Making the organization of work and risk management reliable 194 6.6.1 Quality approach and safety management systems 195 6.6.2 Safety culture 196 6.6.3 Forward planning of skills and workforce – human resources management 197 6.6.4 Managing safety on a daily basis and decision-making 198 6.6.5 Risk analysis, anticipation 199 6.6.6 Adaptation, resilience, emergency and crisis 201 6.6.7 Event analysis and the operating experience feedback process 202 6.6.8 Conducting organizational change 203 6.6.9 Organizing maintenance and subcontractors’ work 204 6.7 Cross-cutting aspects 206 6.7.1 The challenges of integration, organization and time 206 6.7.2 The contribution of the systemic approach 207 6.7.3 Reflexivity and critical approach 209 6.7.4 HOF specialists and HOF relays: the contribution of HOF networks 209 6.8 Conclusion and perspectives 210 6.9 References 211 Chapter 7 From Too Little to Too Much: The Impact of Big Data 225 André Lannoy and Emmanuel Remy 7.1 Introduction 225 7.2 Toward a better understanding? 227 7.2.1 New ways of collecting operation feedback 227 7.2.2 The importance of pre-processing and validation 229 7.2.3 A more accurate vision of the usage profile 230 7.2.4 Toward big data methods 231 7.2.5 Reliability approaches 232 7.2.6 A posteriori processing or visualization 236 7.3 Diagnostics and prognostics 236 7.3.1 Diagnostics 236 7.3.2 The prognostics 238 7.3.3 Classical reliability models for prognostics 239 7.4 Trust 240 7.5 Conclusion and perspectives 241 7.6 References 242 Chapter 8 Conclusions and Prospects 245 André Lannoy 8.1 Nuclear power plants and the progress of reliability 246 8.2 Challenges linked to reliability? 248 8.3 Prospects for future 249 8.3.1 Operational feedback data and data quality 249 8.3.2 On system reliability 250 8.3.3 On the reliability of structures 251 8.3.4 On data from big data and the reliability of equipment 252 8.3.5 On the reliability of organizations and activities 253 8.4 References 255 List of Authors 257 Index 259

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Book SynopsisThis textbook is the first comprehensive and systematic account of the science, technology and policy issues associated with nuclear energy and nuclear weapons. Throughout their account of the evolution of nuclear policy, from its origin to the early Trump presidency, the authors interweave clear technical expositions of the science and technology that underpin and constrain it. The book begins by tracing the early work in atomic physics, the discovery of fission, and the developments that led to the Manhattan Project and the delivery of atomic bombs against Japan that ended World War II. It follows the initial failed attempts at nuclear disarmament, the onset of the Cold War nuclear arms competition, and the development of light water reactors to harness nuclear energy for electric power generation. The authors thoroughly unpack the problem of nuclear proliferation, examining the strategy and incentives for states that have and have not pursued nuclear weapons, and providing an overview of the nuclear arsenals of the current nuclear weapon states. They trace the technical, political and strategic evolution of deterrence, arms control and disarmament policies from the first attempts for an Outer Space Treaty in 1957 through the new START treaty of 2009. At critical junctures in the narrative, the authors explain the relevant nuclear science and technology including nuclear fission and criticality; nuclear materials and enrichment; nuclear detonation and nuclear weapons effects; nuclear weapons stockpile constraints, stewardship and surveillance; nuclear fusion and thermonuclear weapons; technologies for monitoring, verification and proliferation; and nuclear forensics. They conclude with an assessment of contemporary issues ranging from the Joint Comprehensive Plan of Action reached to halt Iran’s nuclear weapons development program, to the threat of nuclear terrorism, the perceived nuclear weapons policies of Russia and China, and the US efforts to provide disincentives for its allies to acquire their own nuclear weapons by maintaining credible security guarantees.Table of Contents1. Early days1.1. Development of atomic physics1.2. Origins of nuclear fission – Great Britain and continental Europe1.3. Nuclear science I – fission and criticality1.3.1. Fission, criticality and the fission chain1.3.1.1. Decay and half-life1.3.2. Energy scale of nuclear reactions relative to chemical reactions1.3.3. Nuclear reactions and cross sections1.3.4. Neutrons basics1.3.4.1. Neutrons from fission (nu-bar)1.3.4.2. Neutron energy and moderation concepts1.3.5. Critical mass, chain reactions, energy and fission products1.3.6. Enrichment and production1.3.7. Worked example – Chicago Pile1.4. The Manhattan Project1.4.1. Organization1.4.2. Key personnel1.4.3. Technical obstacles1.4.4. The path to success1.5. Nuclear science II- materials and enrichment1.5.1. Uranium enrichment1.5.2. Reactor basics and plutonium production1.5.3. Overview of proliferation-resistant fuel cycles and reactors1.5.4. Worked example – centrifuge versus gaseous diffusion1.6. Truman’s decision to drop two atomic bombs1.6.1. Policy options, alternative targets1.6.2. Threat assessment1.6.3. Strategic and tactical considerations1.6.4. Key players and the decision1.6.5. Alternative explanations1.7. Effects of the detonations1.7.1. Blast 1.7.2. Radiation 1.7.3. Shock waves1.7.4. Electromagnetic pulse1.7.5. Estimates of prompt and delayed fatalities1.8. Nuclear science III – nuclear weapons and their effects1.8.1. Basic design concepts1.8.2. Weapon effects1.8.3. Blast and pressure1.8.4. Thermal Effects1.8.5.   Radiation effects1.8.6. Other (EMP, delayed fatalities, impact on climate change)1.8.7. Radiation effects on biological systems1.8.8. Weapons effects in military planning1.8.9. Comparison to conventional weapons and their uses1.8.10. Accuracy and effectiveness1.8.11. Hardening and survivability1.8.12. Worked example – Hiroshima blast and radiation effects 2. Postwar expansion (1946-1968)2.1. National security act, 19472.1.1. National security council2.1.2. US Air Force2.1.3. Central Intelligence Agency2.1.4. Other consequences2.2. Atomic Energy Commission2.2.1. Thermonuclear weapons debate2.2.2. Concern of Soviet weapons capability2.3. Nuclear science IV– fusion and thermonuclear weapons2.3.1. Basics of nuclear fusion2.3.2. Thermonuclear concepts2.3.3. Worked example – to be determined2.4. Failed arms control and onset of the Cold War2.4.1. Acheson-Lillienthal report2.4.2. Failure of the Baruch plan2.4.3. Soviet resistance2.4.4. Korean War (1950-53)2.4.4.1. Role of nuclear weapons2.4.4.2. Beginnings of extended deterrence2.5. Nuclear proliferation begins2.5.1. Mirror Imaging: USSR program, Kurchatov, espionage from Manhattan project2.5.2. USSR weapons test (1949)2.5.3. The UK program and test (1952)2.6. Nuclear arms competition between the US and the USSR2.6.1. The Hydrogen Bomb 2.6.1.1. Oppenheimer vs. Teller2.6.1.2. Lawrence Livermore National Laboratory2.6.2. Early nuclear weapon strategy development2.6.2.1. Massive retaliation and its critics2.6.2.2. Deterrence and Secure 2nd Strike2.6.2.3. Strategic bombers, missiles, the Navy (SSBNS, SLBNS)2.6.2.4. Intercontinental delivery2.6.3. Soviet responses 2.7. Nuclear Science V– modern weapons and the stockpile2.7.1. Constraints and weapon size and mass 2.7.2. Constraints on weapon efficiency and yield2.7.3. Materials properties and equations of state2.7.4. Stockpile surveillance - assessing reliability2.7.5. Worked example – yield and efficiency3. The problem of nuclear proliferation3.1. The International Atomic Energy Agency3.1.1.   Application of nuclear energy for electric power generation3.1.2. Efforts to forestall proliferation3.1.2.1. Nuclear suppliers group3.1.2.2. Zangger committee3.2. Nuclear proliferation builds3.2.1. France – 19603.2.2. China – 19643.2.3. Israel – 19653.2.4. Sweden – ended in 19683.3. First arms control measures3.3.1. Distinction between disarmament and arms control3.3.2. Outer Space Treaty – 19573.3.3. Impact of Cuban Missile Crisis - 19623.3.4. Limited Test Ban Treaty - 1963 3.4. Nuclear science VI– stockpile safety and security3.4.1. Use control concepts3.4.2. Stockpile aging and reliability3.4.3. One-point safety3.4.4. Worked example - decay and aging of weapons material 4. Technical, political and strategic evolution of deterrence and arms control4.1. Declaratory policies4.2. Deterrence policy4.2.1. Red and blue4.2.2. “No First Use” versus “Use to De-escalate”4.3. Extended deterrence and US nuclear deployments4.4. Flexible response4.5. Soviet and US buildup4.6. The importance of missile defense4.7. Nuclear arms control and restraint4.7.1. Nuclear non-proliferation treaty – 19684.7.2. SALT I– 19724.7.2.1. Importance of MIRVS4.7.3. ABM treaty -19724.7.4. SALT II – 19794.7.5. Carter policy of deterring reprocessing of spent fuel - 19774.7.6. Additional proliferation activities4.7.6.1. Indian test – 19744.7.6.2. Pakistani commitment4.7.6.3. German-Brazilian deal4.7.6.4. Taiwan, South Korea initiatives4.7.7.   INF treaty – 19874.7.8. START – 19914.8. Nuclear science VII– monitoring, verification and proliferation4.8.1. Detonation monitoring and detection4.8.2. Safeguards technologies4.8.3. Other measurement concepts and activities4.8.4. Technologies for treaty verification and monitoring4.8.5. Proliferation resistant reactors and fuel cycle4.8.6. Worked example – signature detection 5. The second nuclear age (1992- present)5.1. End of the Cold War5.1.1. START II (1993)5.1.2. Nunn-Lugar and cooperative threat reduction5.2. Ukraine and Kazhakstan nuclear disarmament5.3. Regional proliferation5.3.1. Iraq5.3.2. North Korea5.3.3. Libya5.3.4. India versus Pakistan5.3.5. Iran5.4. Counter-proliferation 5.4.1. Proliferation security initiative5.4.2. Stuxnet5.5. Nuclear disarmament5.5.1. Disarmament and the legitimacy of the non-proliferation regime5.5.2. Historical examples of nuclear disarmament5.5.2.1. South Africa5.5.2.2. Brazil and Argentina5.5.2.3. Former Soviet Union5.6. Comprehensive Test Ban Treaty5.6.1. Failed US. ratification5.6.2. Efforts at START III and completion of Strategic Offensive Arms Reduction Treaty (2002) 5.6.3. US withdrawal from the ABM treaty and its significance5.6.4. New START (2009)5.7. Nuclear science VIII– stockpile stewardship without nuclear testing5.7.1. Contrast with stockpile surveillance5.7.2. High energy density physics experiments5.7.3. Codes and supercomputers5.7.4. Worked example – stockpile surveillance5.7.5. Worked example – computational demands of physics codes 6. Contemporary issues6.1. The Obama nuclear initiatives and their legacy6.1.1. Failed attempts to develop new nuclear weapons (RNEP and RRW)6.1.2. Beyond life extension programs6.1.3. The nuclear security initiatives6.1.4. Strengthening the NPT6.2. Russian adoption of “escalate to deescalate” doctrine6.3. Nuclear weapons and China’s “anti-access/area denial” strategy6.4. Cyber threats to nuclear command and control systems6.5. Nuclear weapons and cross domain deterrence6.5.1. Issues of proportionality and escalation control6.6. Impact of economic sanctions as a counter-proliferation tool6.7. The Iran Joint Comprehensive Plan of Action (JCPOA)6.7.1. Elements of the agreement6.7.2. Strengths and weaknesses6.7.3. Effects on others6.7.4. Consequences6.8. Threat of nuclear terrorism6.8.1. Loss of control of a nuclear weapon6.8.2. Loss of control of nuclear material6.8.3. Loss of control of radioactive material and risks of radioactive dispersal devices6.9. Challenges of attribution, prosecution and retaliation6.9.1. Pre- and post-detonation attribution and forensics6.9.2. Decision-making complexities of cross discipline assessments6.9.3. Policy alternatives in response to nuclear weapon use6.9.4. Accuracy and timeliness requirements6.10. Nuclear science IX – Illicit material detection and forensic attribution6.10.1. Radiation detection and analysis6.10.1.1. Passive detection and spectroscopy6.10.1.2. Activation6.10.1.3. Radiography6.10.2. Nuclear forensics and attribution6.10.2.1. Decay products and chronometry6.10.3. Worked example – standoff detection of special nuclear material 7. Conclusion – Will the “tradition of non-use” of nuclear weapons be sustained? If not, what are the potential consequences?

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Book SynopsisThis book offers a complete panorama of the pressurized water reactor industry, beginning from its origin in the USA and the realization of nuclear engines for naval propulsion, to its most recent developments in the field of civil energy production, particularly in France with the 56 reactors of the multinational electric utility company, Electricité de France (EDF). This comprehensive two-volume masterwork features detailed descriptions of all the crucial components driving a pressurized water nuclear reactor. Volume 1 deals with the main components, such as the main primary circuit, the reactor core, and the steam generators. Volume 2 covers the secondary circuit and the cold source, including components such as the turbine, condenser, alternator, transformers and power supply. Written by Serge Marguet, a leading specialist in reactor physics and author of several books on the subject, this book draws on his experience of more than 35 years in research and development at EDF, a global leader in civil nuclear energy. Featuring a richly illustrated, full-color iconography, as well as a detailed index and bibliography, The Technology of Pressurized Water Reactors is an indispensable work for seasoned nuclear energy professionals, as well as inquisitive newcomers to the field.Table of ContentsHistory of the pressurized water reactor type.- The nuclear island.- The primary circuit.- The vessel and its internals.- Reactor core and fuel.- The secondary circuit.- The main circuits.- The turbine-generator unit and electricity production.- Towards the pressurized water reactors of the 21st century.

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Book SynopsisThis complete introduction to plasma physics and controlled fusion by one of the pioneering scientists in this expanding field offers both a simple and intuitive discussion of the basic concepts of this subject and an insight into the challenging problems of current research. In a wholly lucid manner the work covers single-particle motions, fluid equations for plasmas, wave motions, diffusion and resistivity, Landau damping, plasma instabilities and nonlinear problems. For students, this outstanding text offers a painless introduction to this important field; for teachers, a large collection of problems; and for researchers, a concise review of the fundamentals as well as original treatments of a number of topics never before explained so clearly. This revised edition contains new material on kinetic effects, including Bernstein waves and the plasma dispersion function, and on nonlinear wave equations and solitons. For the third edition, updates was made throughout each existing chapter, and two new chapters were added; Ch 9 on “Special Plasmas” and Ch 10 on Plasma Applications (including Atmospheric Plasmas). Table of ContentsIntroduction.- Single-particle motions.- Plasmas as fluids.- Waves in plasmas.- Diffusion and resistivity.- Equilibrium and stability.- Kinetic theory .- Nonlinear effects.- Special plasmas.- Plasma applications.

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Book SynopsisTable of Contents1. Einige Grundlagen zur Kernphysik.- 1.1 Zur Erinnerung einiges über die Sprachregelung.- 1.2 Die drei Säulen der Kernphysik.- 1.3 Werkzeuge der Kernphysik.- 1.3.1 Beschleuniger.- 1.3.2 Detektoren.- 1.4 Streuprobleme.- 1.5 Bemerkungen zur Statistik.- 1.6 Zum Problem der Kernkräfte.- Literatur.- 2. Kernzerfälle und Kernreaktionen.- 2.1 Kernzerfälle.- 2.1.1 ?-Zerfall.- 2.1.2 Kernspaltung.- 2.2 Kernreaktionen.- 3. Einführung in die Neutronenphysik.- 3.1 Theoretische Grundlagen.- 3.1.1 Entdeckung und Eigenschaften des Neutrons.- 3.1.2 Wechselwirkung von Neutronen mit Materie (Begriff des Wirkungsquerschnitts).- 3.1.3 Experimenteller Nachweis von Neutronen.- 3.1.4 Intensive Neutronenquellen.- 3.2 Anwendungen.- 3.2.1 Anwendung von langsamen Neutronen zur Strukturuntersuchung.- 3.2.2 Herstellung von Radioisotopen.- 3.2.3 Neutronenzyklus in Reaktoren.- 3.2.4 Kernwaffen.- 4. Kernreaktoren.- 4.1 Einleitung.- 4.1.1 Energie aus Kernspaltung.- 4.1.2 Rohstoffe für Kernspaltung.- 4.1.3 Brut- und Konverter-Reaktoren.- 4.1.4 Kernreaktoren.- 4.2 Reaktorphysik.- 4.2.1 Bindungsenergie und Kernmassen.- 4.2.2 Neutronenreaktionen und Wirkungsquerschnitte.- 4.2.3 Induzierte Kernspaltung.- 4.2.4 Neutronenreaktionen in verschiedenen Systemen.- 4.3 Reaktortechnik.- 4.3.1 Kraftwerksysteme.- 4.3.2 Kraftwerkstechnik.- 4.3.3 Reaktorsicherheit.- 5. Reaktorsicherheit.- 5.1 Funktion eines Kernkraftwerkes.- 5.2 Aufgabe der Reaktorsicherheit.- 5.3 Sicherheitskonzept.- 5.4 Betriebserfahrungen.- 6. Umweltprobleme.- 6.1 Einleitung.- 6.2 Bedeutung und Notwendigkeit des Einsatzes von Energie.- 6.2.1 Energiebedarf.- 6.2.2 Energieverbrauch und Bruttosozialprodukt.- 6.2.3 Der soziale Ertrag des Energieeinsatzes.- 6.2.4 Prognose des Wachstums.- 6.2.5 Grenzen des Energieverbrauchs.- 6.3 Schadstoffe.- 6.3.1 Industrielle Schadstoffproduktion.- 6.3.2 Schadstoffe aus Verbrennungsprozessen.- 6.3.3 Umweltschäden durch Schwefel- und Stickoxide.- 6.3.4 Das CO2-Klimaproblem.- 6.4 Belastung durch Umweltstrahlung.- 6.4.1 Strahlungsmeßgrößen.- 6.4.2 Mittlere Strahlenbelastung der Bevölkerung.- 6.4.3 Kurzzeitbestrahlung und hohe Dosen.- 6.4.4 Langzeitexposition und Strahlenschutzverordnung.- 6.5 Kernkraftwerke und Umwelt.- 6.5.1 Abwärme und Abluft.- 6.5.2 Abwasser.- 6.5.3 Abfallprodukte und Zwischenlagerung.- 6.5.4 Wiederaufarbeitung.- 6.5.5 Endlagerung.- 6.6 Vergleiche.- 6.6.1 Emissionswirkungen.- 6.6.2 Spätfolgen.- 6.6.3 Aktuelle Menschheitsrisiken.- 6.6.4 Nachwort.- 7. Kernfusion in magnetisch eingeschlossenen Plasmen.- 7.1 Auswahl der Fusionsreaktionen.- 7.2 Tokamaks-Stellaratoren-Siegelmaschinen.- 8. Nachweis von Kernstrahlung.- 8.1 Grundlagen.- 8.1.1 Einleitung.- 8.1.2 Die Aufgaben eines Teilchendetektors.- 8.1.3 Die Verarbeitung der Kernstrahlimpulse.- 8.1.4 Zählstatistik.- 8.2 Nachweis geladener Teilchen.- 8.2.1 Durchgang geladener Teilchen durch Materie.- 8.2.2 Gas-Ionisations-Kammern.- 8.2.3 Gas-Proportionalzähler.- 8.2.4 Geiger-Müller-Zählrohre.- 8.2.5 Halbleiterzähler.- 8.2.6 Szintillationszähler.- 8.2.7 ?erenkov-Zähler.- 8.2.8 Andere Nachweisverfahren.- 8.2.9 Teilchenidentifizierung mit Zählern.- 8.3 Nachweis ungeladener Teilchen.- 8.3.1 Grundlegende Bemerkungen.- 8.3.2 Nachweis von Neutronen.- 8.3.3 Nachweis von Gammastrahlung.- 8.3.4 Nachweis von Neutrinos.- 8.4 Ausblick.- 8.5 Weiterführende Literatur.- 9. Konzepte zur Energienutzung.- 9.1 Energievorräte und Energieverbrauch.- 9.2 „Verschwendung“ bei thermischen Kraftwerken.- 9.2.1 Bessere Nutzung durch Heizkraftwerke.- 9.2.2 Bessere Nutzung durch Vorschaltprozesse.- 9.3 „Verschwendung“ in Haushaltungen.- 9.4 „Verschwendung“ im Verkehr.- 9.5 „Neue“ Energiequellen.- 9.5.1 Sonnenenergie.- 9.5.2 Hochtemperaturreaktoren.- 9.5.3 Fusionsreaktor.- 9.5.4 Energieeinsparung in Haushalten und Industrie.- Sachwortverzeichnis.

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Book SynopsisDieses Buch zeigt am Beispiel des komplexen Themas Entsorgung radioaktiver Reststoffe die Herangehensweise für disziplinübergreifende Zusammenarbeit und die transdisziplinäre Verknüpfung von Wissenschaft und Öffentlichkeit. Es bietet Praxisbezogene Vorschläge aus einem Forschungsprojekt zur Problematik der wissenschaftlichen Vorbereitung der Endlagersuche sowie wissenschaftstheroetische Hintergründe zur inter- und transdisziplnären Zusammenarbeit. Das Buch richtet sich an Dozenten und Wissenschaftler sowie Entscheidungsträger in Verwaltung und Politik.Table of ContentsInterdisziplinarität – Transdisziplinarität.- Radioaktive Reststoffe.- Politikwissenschaften, Geologie, Geochemie, Rechtswissenschaft und Strahlenschutz.- Risiko, Risikobegriff, Risikoverständnis.- Das Konzept der Freiwilligkeit.- Interdisziplinäre Kooperation.- Organisation interdisziplinärer Zusammenarbeit.

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Book SynopsisDieses Buch gibt einen Überblick über den Umgang mit radioaktiven Reststoffen. Es zeigt auf, welche Quellen für radioaktive Abfälle es gibt, wie die Optionen Zwischenlagerung und Endlagerung gestalte sind, sowie, welche Problem sich aus dem Transport radioaktiver Stoffe ergeben. Schließlich beschreibt es noch die Möglichkeit der Transmutation - also die Elementumwandlung durch gezielte Kernreaktionen - und eine dazugehörige Anwendung.Table of ContentsEinleitung.- Radioaktivität.- Zerfallsgesetze.- Quellen radioaktiven Materials.- Aufbereitung.- Zwischenlagerung.- Endlagerung.- Transport.- Organisationen (international, Deutschland).- Transmutation.- Transmutation physikalische Grundlagen.- Transmutation existierende Verfahren.- Spaltprodukt-Transformator.

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Book SynopsisThis publication documents the results of an IAEA coordinated research project (CRP)on the application of computational fluid dynamics (CFD) codes for nuclear power plant design. The main objective was to benchmark CFD codes, model options and methods against CFD experimental data under single phase flow conditions. This publication summarizes the current capabilities and applications of CFD codes, and their present qualification level, with respect to nuclear power plant design requirements. It is not intended to be comprehensive, focusing instead on international experience in the practical application of these tools in designing nuclear power plant components and systems. The guidance in this publication is based on inputs provided by international nuclear industry experts directly involved in nuclear power plant design issues, CFD applications, and in related experimentation and validation highlighted during the CRP.

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Book SynopsisThis Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.4, which it supersedes. The revised version provides specific recommendations on developing, formulating and presenting the operational limits and conditions as well as the operating procedures for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. The recommendations in this publication are intended for use by operating organizations of research reactors, regulatory bodies and other relevant organizations involved in a research reactor project.

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Book SynopsisThe operational useful lifetime of semiconductor electronic devices working in harsh radiation environments is limited by the structural defects induced by the exposure to ionizing radiation. This has immediate consequences for their use in high radiation environments, for example in nuclear facilities, satellites, radiotherapy, medical diagnostics, security and other industries. This publication establishes a standardized procedure to quantify the radiation hardness of semiconductor diode materials in a way that is independent of the irradiation parameters and biasing conditions of the device. The established parameter reflects the additional free charge carrier trapping cross section induced by the damaging radiation, normalized to the predicted concentration of generated vacancies by the same radiation. The effectiveness of the approach is validated through different types of ion beam irradiations, characterizations and materials used. The work leads towards approaches to predict the radiation induced effects on device performance for more complex electronic structures.

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Book SynopsisOn request, the IAEA performs comprehensive audits of radiotherapy programmes to assess the whole process, including aspects such as organization, infrastructure and clinical and medical physics components. The objective of a comprehensive clinical audit is to review and evaluate the quality of all components of the practice of radiotherapy at the institution, including its professional competence, with a view to quality improvement. A multidisciplinary team, known as Quality Assurance Team in Radiation Oncology (QUATRO), comprising a radiation oncologist, a medical physicist and a radiation therapist, are required to carry out the audit. The present publication provides revisions of the QUATRO guidelines published in 2007, by incorporating new procedures relevant to newer technologies and modalities that have become routinely used in radiotherapy centres in the interim period.

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Book SynopsisThis Safety Guide provides specific recommendations on protection against internal and external hazards in the operation of nuclear power plants. It provides new or updated recommendations derived from enhanced understanding of operational aspects of hazards and combinations of hazards. Operating experience gained from incidents and accidents in nuclear power plants around the world has demonstrated that fire can be an important risk contributor in many Member States. However, there are other internal and external hazards that have also to be considered in the design and operation of nuclear power plants. This Safety Guide supersedes and expands the scope of lAEA Safety Standards Series No. NS- G-2. 1, Fire Safety in the Operation of Nuclear Power Plants, to include recommendations on these other hazards.

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Book SynopsisA revision of IAEA Nuclear Security Series No. 2, Nuclear Forensics Support, which was published in 2006. Since then, there has been substantive expansion and confidence in the application of nuclear forensics globally to effectively counter the threat of nuclear and other radioactive materials out of regulatory control.

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Book SynopsisThis Safety Guide provides recommendations on radiation protection and radioactive waste management in the design and operation of research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It identifies important components that should be considered at the design stage with regard to facilitating radiation protection and radioactive waste management. It also recommends good practices in implementing operational radiation protection and radioactive waste management programmes, and in their optimization. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.6, which it supersedes.

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Book SynopsisThis publication is a revision and combination of two Safety Guides, IAEA Safety Standards Series No. NS-G-1.1 and No. NS-G-1.3. The revision takes into account developments in instrumentation and control (I&C) systems since the publication of the earlier Safety Guides. The main changes relate to the continuing development of computer applications and the evolution of the methods necessary for their safe, secure and practical use. In addition, account is taken of developments in human factors engineering and the need for computer security. This Safety Guide also references and takes into account other IAEA safety standards and IAEA Nuclear Security Series publications that provide guidance relating to I&C design.

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Book SynopsisThis publication provides guidance for assessing the sustainability of a nuclear energy system (NES) in the area of nuclear fuel cycle facility (NFCF) safety. It deals with NFCFs that may be potentially involved in the NES such as, mining, milling, refining, conversion, enrichment, fuel fabrication, spent fuel storage, and spent fuel reprocessing facilities. It augments the information presented in the earlier INPRO publications on the methodology for sustainability assessments. The publication is intended for use by organizations involved in the development and deployment of a NES, including planning, design, modification and technical support for NFCFs.

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Book SynopsisControl of nuclear material comprises the administrative and technical measures applied to ensure that nuclear material is not misused or removed from its assigned location without approval and/or without proper accounting. This publication, which builds upon the Implementing Guide IAEA Nuclear Security Series No.25-G , focuses on the control of nuclear material during storage, use and movement using a facility's nuclear material accounting and control (NMAC) system. It describes practical measures for controlling nuclear material for nuclear security purposes during all activities at a facility, including movements, and how to use a graded approach in applying such measures. The technical guidance provided is targeted at States and their competent authorities on how to use individual elements of the NMAC system, but will be also useful for persons responsible for designing, operating and assessing nuclear security systems, physical protection of nuclear facilities, nuclear security management, operators and managers of NMAC systems; as well as for those preparing associated regulations; and persons responsible for computer security at nuclear facilities.

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Book SynopsisThis Safety Guide provides practical guidance and recommendations on ageing management for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It is intended for use by operating organizations in establishing, implementing and improving ageing management programmes for research reactors, and by regulatory bodies in verifying that ageing of research reactors is being effectively managed. The Safety Guide focuses on managing the physical ageing of systems, structures and components important to safety, and also provides guidance on safety aspects of managing obsolescence. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-10, which it supersedes.

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Book SynopsisThis publication provides specific recommendations on research reactor instrumentation and control systems and software important to safety, including instrumentation and control system architecture and associated components, from sensors to actuators, operator interfaces and auxiliary equipment, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. The recommendations and guidance apply to both the design and configuration management of instrumentation and control systems for new research reactors and the modernization of the instrumentation and control systems at existing research reactor facilities. In addition, this Safety Guide provides recommendations and guidance on human factors engineering and human-machine interfaces, and for computer based systems and software for use in instrumentation and control systems important to safety. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-37, which it supersedes.

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Book SynopsisDecommissioning is the last step in the lifetime management of an authorized facility and it must be considered during the design, construction, commissioning and operation of such facilities. This publication provides guidance on how to comply with requirements for the safe decommissioning of nuclear power plants, research reactors, and other nuclear fuel cycle facilities. It addresses all the aspects of decommissioning that are required to ensure safety including: roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and completion of decommissioning. It is intended for use by those working in policy and strategy development, planning, implementation and regulatory control of decommissioning.

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Book SynopsisThis Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

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Book SynopsisThis publication describes the purpose and scope of the INPRO service Analysis Support for Enhanced Nuclear Energy Sustainability (ASENES) and its potential benefits to Member States. The publication highlights the links between this service and overall technical support to Member States for the planning and development of nuclear energy, and explains how it integrates with other IAEA services supporting knowledgeable decision making on nuclear power. An overview of analytical tools developed by INPRO for this purpose is also provided.

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Book SynopsisNuclear security culture is an important component of an effective nuclear security regime, as it serves as a tool to improve the performance of the human component at nuclear facilities and organizations to counter both insider and outsider threats. Security culture connotes not only the technical proficiency of the people but also their awareness of security risks and motivation to follow established procedures, comply with regulations and take the initiative when unforeseen circumstances arise. A workforce made up of individuals who are vigilant, who question irregularities, execute their work diligently and exhibit high standards of personal and collective behaviour is able to achieve effective nuclear security. Building upon this understanding of the importance of a strong nuclear security culture, this publication provides practical guidance on how to implement a systematic nuclear security culture enhancement programme.

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Book SynopsisThis Safety Report has been developed as part of the IAEA programme on occupational radiation protection to provide for the application of its safety standards in implementing a graded approach to the protection of workers against exposures associated with uranium mining and processing. The publication describes the methods of production associated with the uranium industry and provides practical information on the radiological risks to workers in the exploration, mining and processing of uranium. It is a compilation of detailed information on uranium mining and processing stages and techniques, general radiation protection considerations in the relevant industry, general methodology applicable for control, monitoring and dose assessment, exposure pathways, and radiation protection programs for the range of commonly used mining and processing techniques.

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Book SynopsisThis publication gives practical information and examples on safety analysis principles and methods as well as the contents of licensing documentation needed to support application of IAEA safety standards to nuclear fuel cycle facilities. A systematic methodology is presented, covering the establishment of acceptance criteria, hazard evaluation, identification of postulated initiating events, analysis of accident sequences and consequences. Information is also provided on application of the results of the safety analysis in the design and operational phases, and on appropriate management system processes. The publication applies to all lifetime stages of relevant facilities and for modifications and upgrades. The information presented may be used for periodic safety reviews and consideration of extended lifetime of facilities. With respect to licensing documentation, the publication provides indicative contents and format of the safety analysis report as a higher level document that incorporates the information required at various steps in the licensing and re-licensing process.

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Book SynopsisThe transport of radioactive material is an essential activity worldwide. Both safety and security during transport are matters of national and international importance. This publication is the latest edition of the IAEA Safety Requirements for the safe transport of radioactive material. It is supported by six IAEA Safety Guides which provide explanation and guidance for the SSR-6 requirements to facilitate harmonized implementation. The SSR-6 Regulations apply to the transport of radioactive material by all modes on land, water, or in the air, including transport that is incidental to the use of the radioactive material.Transport comprises all operations and conditions associated with, and involved in, the movement of radioactive material; these include the design, manufacture, maintenance and repair of packaging, and the preparation, consigning, loading, carriage including in-transit storage, unloading and receipt at the final destination of loads of radioactive material and packages. These requirements form an integral part of regulations worldwide, therefore SSR-6 and its associated guidance documents are a requisite source of guidance information for governments, regulators, and all individuals involved in the aforementioned activities of transport of radioactive material.These requirements are adopted into the UN Model Regulations which are subsequently adopted by the IMDG Code by the International Maritime Organisation for shipment by sea and by the International Civil Aviation Organization Technical Instructions for shipment by air. Both the IMDG Code and the ICAO Technical Instructions are globally implemented and mandatory. Land transport is the responsibility of the national government of each Member State, and the SSR-6 requirements are adopted for national transport safety regulations for shipments on land.

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Book SynopsisThis Safety Guide provides recommendations on how to meet the requirements of IAEA Safety Standards Series No. SSR?2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, in relation to fuel handling and storage systems. The publication addresses the design aspects of handling and storage systems for fuel that remain part of the operational activities of a nuclear reactor. It covers the following stages of fuel handling and storage in a nuclear power plant: receipt, storage and inspection of fresh fuel before use and transfer of fresh fuel into the reactor; removal of irradiated fuel from the reactor and transfer of the irradiated fuel to the spent fuel pool; and reinsertion of irradiated fuel from the spent fuel pool into the reactor. Recommendations are also provided on the storage, inspection and repair of irradiated or spent fuel in the spent fuel pool, and the preparation for the removal of this fuel from the spent fuel pool and on the handling of fuel casks in the spent fuel pool and on their transfer.

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Book SynopsisThis publication reports on the DACCORD project, which supports Member States in preparing preliminary cost estimates for the decommissioning of research reactors. The report is of particular benefit to programmes with limited decommissioning experience. Costing projects for the decommissioning of research reactors can be broad in scope with many possible inputs and influences that require due consideration in developing the estimate. The publication provides information on unit factors for research reactor decommissioning and a basis for estimating uncertainties and contingencies and for assessing the impact of decommissioning planning and characterization activities. It also addresses the use of the CERREX?D2 (Cost Estimate for Research Reactors in Excel) software code, developed by the IAEA to enable non?specialist users to develop preliminary cost estimates for decommissioning.

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Book SynopsisThis Safety Requirements publication takes into account and incorporates developments relating to site evaluation for nuclear installations since the publication of IAEA Safety Standards Series No. NS-R-3 in 2003. It applies IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. Requirements for site evaluation are intended to contribute to the adequate protection of site personnel and the public and protection of the environment from harmful effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements evolve with these advances and this publication reflects the present consensus among States.

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Book SynopsisWithin the nuclear field, a vast body of knowledge, involving scientific, technical and managerial fields, is distributed among many organizations of different types. Managing and provisioning distributed knowledge is therefore becoming one of the major challenges in federated organizational environments. This publication provides information to organizations dealing with nuclear knowledge and its management. It covers an introduction to semantic information technologies, the Worldwide Web standards developed for interoperability, the construction of knowledge bases on the basis of distributed knowledge, and the development of knowledge driven applications. In addition to providing insight into the development of distributed knowledge bases, the intent of this publication is to provide examples of applications of semantic technologies specifically in the nuclear field.

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Book SynopsisThis Safety Guide provides recommendations on the establishment of a framework for safety in accordance with the IAEA safety standards for States deciding on and preparing to embark on a nuclear power programme. In this regard, it proposes 197 safety related actions to be taken in the first three phases of the development of the nuclear power programme, to achieve the foundation for a high level of safety throughout the entire lifetime of the nuclear power plant (NPP). This includes safety in the construction, commissioning, and operation of the NPP and the associated management of radioactive waste and spent fuel, and safety in decommissioning. Thus, it contributes to the building of leadership and management for safety and of an effective safety culture and serves as guidance for self-assessment by all organizations involved in the development of a safety infrastructure.

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Book SynopsisThis new revision provides guidance to States and their competent authorities on how to establish or improve, implement, maintain and sustain the elements of the nuclear security regime related to radioactive material, associated facilities and activities, with particular emphasis on the development of regulatory requirements. The publication applies to the security of radioactive material in use or in storage as well as associated facilities and associated activities and assists Member States in their regimes against unauthorized removal of the radioactive material or sabotage performed with the intent to cause harmful radiological consequences.

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Book SynopsisProbabilistic methods are increasingly being used to complement deterministic methods in assessing the safety and ensuring the reliability of research reactors. Addressing features specific to research reactors, this publication suggests a practical approach for the development and implementation of a project using probabilistic methods in terms of objective, scope, data and modelling, as well as the application of results to enhance safety and reliability. This publication is intended to be used by operating organizations, regulatory bodies and technical support organizations when performing or reviewing research reactor assessments in which probabilistic methods are applied. It will ideally be read in conjunction with relevant IAEA Safety Standards Series publications and technical guidelines for safety analysis, operation and maintenance, and component reliability data for research reactors.

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Book SynopsisThe IAEA has developed a comprehensive methodology for evaluating nuclear security culture. When implemented by a State, this methodology will help to make nuclear security culture sustainable. It will also promote cooperation and the sharing of good practices related to nuclear security culture. This publication is the first guidance for assessing nuclear security culture and analysing its strengths and weaknesses within a facility or activity, or an organization. It reflects, within the context of assessment, the nuclear security culture model, principles and criteria set out in the Implementing Guide, IAEA Nuclear Security Series No. 7. This guidance will be useful for organizations and operating facilities in conducting the self-assessment of nuclear security culture by providing practical methods and tools. It will also help regulatory bodies and other competent authorities to understand the self-assessment methodology used by operators, encourage operators to start the self-assessment process or, if appropriate, conduct independent assessments of nuclear security culture.

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