On September 27 - October 3, 2008 the NATO Advanced Research Workshop (ARW) on progress in high-energy physics and nuclear safety was held in Yalta, Crimea (see: http: //crimea.bitp.kiev.ua and http: //arw.bitp.kiev.ua). Nearly 50 leading experts in high-energy and nuclear physics from Eastern and Western Europe as well as from North America participated at the Workshop. The topics of the ARW covered recent results of theoretical and experimental studies in high-energy physics, accelerator, detection and nuclear technologies, as well as problems of nuclear safety in high-energy experimentation and in nuclear - dustry. The forthcoming experiments at the Large Hadron Collider (LHC) at CERN and cosmic-ray experiments were among the topics of the ARW. An important aspect of the Workshop was the scienti?c collaboration between nuclear physicists from East and West, especially in the ?eld of nuclear safety. The present book contains a selection of invited talks presented at the ARW. The papers are grouped in two part

Introduces Novel Applications for Solving Neutron Transport Equations While deemed nonessential in the past, fractional calculus is now gaining momentum in the science and engineering community. Various disciplines have discovered that realistic models of physical phenomenon can be achieved with fractional calculus and are using them in numerous ways. Since fractional calculus represents a reactor more closely than classical integer order calculus, Fractional Calculus with Applications for Nuclear Reactor Dynamics focuses on the application of fractional calculus to describe the physical behavior of nuclear reactors. It applies fractional calculus to incorporate the mathematical methods used to analyze the diffusion theory model of neutron transport and explains the role of neutron transport in reactor theory. The author discusses fractional calculus and the numerical solution for fractional neutron point kinetic equation (FNPKE), introduces the technique for efficient and accurate numerical computation for FNPKE with different values of reactivity, and analyzes the fractional neutron point kinetic (FNPK) model for the dynamic behavior of neutron motion. The book begins with an overview of nuclear reactors, explains how nuclear energy is extracted from reactors, and explores the behavior of neutron density using reactivity functions. It also demonstrates the applicability of the Haar wavelet method and introduces the neutron diffusion concept to aid readers in understanding the complex behavior of average neutron motion. This text: Applies the effective analytical and numerical methods to obtain the solution for the NDE Determines the numerical solution for one-group delayed neutron FNPKE by the explicit finite difference method Provides the numerical solution for classical as well as fractional neutron point kinetic equations Proposes the Haar wavelet operational method (HWOM) to obtain the numerical approximate solution of the neutron point kinetic equation, and more Fractional Calculus with Applications for Nuclear Reactor Dynamics thoroughly and systematically presents the concepts of fractional calculus and emphasizes the relevance of its application to the nuclear reactor.

This book presents a comprehensive, systematic analysis of Russia- Iran relations in the period following the collapse of the Soviet Union in 1991. It discusses the key areas - such as trade, arms sales, nuclear developments, and potential areas of friction in the Caspian Sea - where co-operation is possible; charts different phases of increasing and declining co-operation; and relates these changes to security considerations and domestic factors in both countries. Throughout, the book argues that the potential for co-operation between the two countries is much greater than people realize, and it concludes by assessing how Russia-Iran relations are likely to develop in future.

The identification and assessment of threats provides an essential basis for the selection, design, and implementation of nuclear security measures. For nuclear material and other radioactive material that is under regulatory control, and associated facilities and activities, the results of this identification and assessment are expressed as a design basis threat or representative threat statement describing the intentions and capabilities of potential adversaries against which the materials and associated facilities and activities are to be protected. An Implementing Guide was issued in 2009 under the title of Development, Use and Maintenance of the Design Basis Threat which was updated and revised. The result of this revision is the current publication. It provides a step?bystep methodology for conducting a national nuclear security threat assessment including both physical and computer security aspects, and for the development, use and maintenance of design basis threats and representative threat statements.

Five years after the one of the worst nuclear accidents in history, Fukushima now only occasionally headlines national and international media. However, the disaster is far from over, as evidenced by a hundred thousand people from Fukushima still in the state of evacuation, rising levels of radiation in streams and rivers, and failing attempts to control the leakage of radioactive materials at the Fukushima Daiichi Nuclear Power Plant. Despite these dismal conditions, efforts to recover and rebuild livelihoods in the afflicted regions of Fukushima did start immediately after the outset of the accident. Rebuilding Fukushima gives an account of how citizens, local governments, and businesses responded to and coped with the crisis of Fukushima. It addresses principles to guide reconstruction and international policy environments in which the current disaster is situated. It explores how reconstruction is articulated and experienced at different spatial scales, ranging from individuals to communities and municipalities, and details recovery efforts, achievements, and challenges in the realms of public transportation, agriculture and food production, manufacturing industries, retail sectors, and renewable-energy industries. This book also critically investigates the nature of the current reconstruction policy schemes, and seeks to articulate what may be required in order to achieve more sustainable and equitable (re)development in afflicted regions and other nuclear host regions. Drawing on extensive fieldwork and local surveys, this volume is one of the first books in English that captures the knowledge and insights of native Japanese social scientists who dealt with the complexities of nuclear disaster on a day-to-day basis. It will be of great interest to students and scholars of disaster-management studies and nuclear policy.

This book offers a comprehensive assessment of the dynamics driving, and constraining, nuclear power development in Asia, Europe and North America, providing detailed comparative analysis. The book formulates a theory of nuclear socio-political economy which highlights six factors necessary for embarking on nuclear power programs: (1) national security and secrecy, (2) technocratic ideology, (3) economic interventionism, (4) a centrally coordinated energy stakeholder network, (5) subordination of opposition to political authority, and (6) social peripheralization. The book validates this theory by confirming the presence of these six drivers during the initial nuclear power developmental periods in eight countries: the United States, France, Japan, Russia (the former Soviet Union), South Korea, Canada, China, and India. The authors then apply this framework as a predictive tool to evaluate contemporary nuclear power trends. They discuss what this theory means for developed and developing countries which exhibit the potential for nuclear development on a major scale, and examine how the new "renaissance" of nuclear power may affect the promotion of renewable energy, global energy security, and development policy as a whole. The volume also assesses the influence of climate change and the recent nuclear accident in Fukushima, Japan, on the nuclear power industry's trajectory. This book will be of interest to students of energy policy and security, nuclear proliferation, international security, global governance and IR in general.

Artificial intelligence (AI) methods have had significant impacts in science and technology in recent years. These methods for generating models from datasets or logic-based algorithms that emulate aspects of human performance can similarly accelerate the fields of nuclear applications, science, and technology toward the IAEA goals of contributing to peace, health, and prosperity. This publication provides a review of the current state of the art, outlines challenges and identifies priorities for future AI activities in the nuclear field and the IAEA's role to support their accomplishment. The uses of AI in the fields of nuclear sciences and applications, nuclear power, nuclear safety and security and safeguards verification, are considered. There is also a dedicated chapter on ethics pertinent to AI in the nuclear field.

Developments at the nanoscale are leading to new possibilities and challenges for nuclear applications in areas ranging from medicine to international commerce to atomic power production/waste treatment. Progress in nanotech is helping the nuclear industry slash the cost of energy production. It also continues to improve application reliability and safety measures, which remain a critical concern, especially since the reactor disasters in Japan. Exploring the new wide-ranging landscape of nuclear function, Atomic Nanoscale Technology in the Nuclear Industry details the breakthroughs in nanoscale applications and methodologies that are revolutionizing power production, biotechnology, and material science. Developments in atomic nanoscale technology have given us the ability to: Use ion beams to Investigate and optimize radiation energy losses at the nanoscopic level Assess nanoscopic safety circumstances involved in a reactor failure Analyze characteristics of nuclear spacecraft operating in the nanogravity of deep space Evaluate light collection enhancement for digital X-ray detection Apply brachytherapy using radioisotopes for cancer therapy Treat nuclear waste at the nanoscopic level Use systems-thinking decision making to analyze financial progress of nanotech in the energy industry Assess safety (and safety management methods) for nuclear nanomaterials used in plant operations Representing a first step in multi-combinatorial research, this text incorporates advanced studies that use Monte Carlo and solid-state measurement (including radiation detection) methods. Researchers used these to demonstrate the potential to upgrade methods of radiation protection and nuclear reactor operation (safety, waste disposal, etc.). The author also addresses how we can use nanotechnology to address industrial concerns and enhance nuclear medicine techniques. He highlights several nanomaterial systems and devices to illustrate developments in this area. About the Author: Taeho Woo launched the specialized field of atomic multinology (interdisciplinary research of nuclear technology), which combines the application of information technology, biotechnology, and nanotechnology in the nuclear industry.

Dynamics and Control of Nuclear Reactors presents the latest knowledge and research in reactor dynamics, control and instrumentation; important factors in ensuring the safe and economic operation of nuclear power plants. This book provides current and future engineers with a single resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic characteristics of pressurized light-water reactors, boiling light-water reactors, pressurized heavy-water reactors and molten-salt reactors. It also provides pertinent, but less detailed information on small modular reactors, sodium fast reactors, and gas-cooled reactors.

The first book to look at how energy companies can develop brands as they move to more sustainable energy solutions. The world is facing climate crisis, and never before has the world been looking at the energy industry to solve the delivery of power in ways that do not damage the planet. Includes insights from energy business leaders and is therefore more than an academic thesis, but a practical guide to resolving these branding and sustainability challenges.

This publication outlines the concepts and models supporting the requirements for understanding organizational competence within the nuclear context. It aims to help in the development of organizational competencies in countries with an existing nuclear power capability and those wishing to embark on a nuclear power programme. The publication summarizes necessary processes for mapping organizational competencies, as well as tools and techniques used for assessing them. Specific information provided in this publication will help organizations to determine competence needs based on strategic/corporate objectives and business processes, and to identify their existing success factors.

The IAEA organizes International Collaborative Standard Problems (ICSPs) to facilitate co-operation on advancing reactor technology related activities. These activities include the development, assessment and validation of computer codes for design and safety analysis of nuclear power plants. The objective of this ICSP was to develop and facilitate open access to a set of standardized numerical test problems for selected postulated transients in pressurized heavy water reactors (PHWRs). These manufactured test problems are different from typical benchmark problems in that the specification is designed for a stylized model of a generic CANDU-6 PHWR and a reference solution is not postulated. The set of standardized numerical test problems supports the development of simulation codes, methods, and coupling frameworks. This publication provides a description of four numerical test problems, the participants' individual multi-physics methodologies applied, and simulations carried out, an independent synthesis of the results, and the lessons learned from the exercise.

To address the challenges posed by climate change, and to achieve the goals established in the 2015 Paris Agreement, nuclear power has been identified to have great potential to contribute to the 1.5°C climate change mitigation target. This topical conference on climate change and the role of nuclear power, the first of its kind, served as a unique forum for exchanging science-based information on the role of nuclear power in supporting the low carbon energy transformation and for conducting objective discussions on the opportunities and challenges of safe, secure and safeguarded nuclear technology development. The major themes of the conference covered energy and climate change policies, implications for the power sector, environmental perspectives and potential roles of existing, evolutionary and innovative nuclear power systems, including the integration of nuclear/renewable energy systems. In addition to nuclear power’s interim and long term contributions, some strategic and cross-cutting issues relating to public perception, regulations, markets and finance were also addressed. These proceedings provide a summary of the different plenary, technical and side event sessions as well as the full text of the speeches delivered in the opening, closing and high-level plenary sessions of the conference.

This 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.

This publication provides a comprehensive summary of experiences and results collected at a series of technical meetings of Member States currently operating CANDU-type nuclear power plants. Special emphasis is placed on supporting future harmonization in the regulatory framework, level 1 PSA methodologies and tools and level 1 PSA scope. In addition, information is shared on actions undertaken in response to lessons learned from the Fukushima Daiichi accident.

A properly established governmental, legal and regulatory framework for safety provides for the effective regulatory control of facilities and activities with radiation sources. An important aspect of a regulatory framework is to ensure that the implementation of the regulatory programme is commensurate with the radiation risks associated with facilities and activities, in accordance with a graded approach. This publication provides practical guidance on the application of a graded approach in regulating the safety of radiation sources. Examples of applying this approach in some Member States are included. The proposed methodologies promote a systematic and consistent approach to regulating in accordance with the IAEA safety standards.

As part of the IAEA programme on International Generic Ageing Lessons Learned (IGALL), this publication provides a summarized description of internationally accepted practices. Examples of the national approaches to ageing management for the specific periods of extended shutdown, delayed construction and post final shutdown as applied in the nuclear power plants of participating IGALL Member States are presented. In addition, some of the information is also applicable for the evaluation of ageing effects prior to and after restarting operation. The publication complements existing IAEA publications on ageing management approaches of Member States during normal operation and is intended for use by regulatory bodies, operating organizations, manufacturers, designers and technical support organizations.

Explains the mechanisms governing flow-induced vibrations and helps engineers prevent fatigue and fretting-wear damage at the design stage Fatigue or fretting-wear damage in process and plant equipment caused by flow-induced vibration can lead to operational disruptions, lost production, and expensive repairs. Mechanical engineers can help prevent or mitigate these problems during the design phase of high capital cost plants such as nuclear power stations and petroleum refineries by performing thorough flow-induced vibration analysis. Accordingly, it is critical for mechanical engineers to have a firm understanding of the dynamic parameters and the vibration excitation mechanisms that govern flow-induced vibration. Flow-Induced Vibration Handbook for Nuclear and Process Equipment provides the knowledge required to prevent failures due to flow-induced vibration at the design stage. The product of more than 40 years of research and development at the Canadian Nuclear Laboratories, this authoritative reference covers all relevant aspects of flow-induced vibration technology, including vibration failures, flow velocity analysis, vibration excitation mechanisms, fluidelastic instability, periodic wake shedding, acoustic resonance, random turbulence, damping mechanisms, and fretting-wear predictions. Each in-depth chapter contains the latest available lab data, a parametric analysis, design guidelines, sample calculations, and a brief review of modelling and theoretical considerations. Written by a group of leading experts in the field, this comprehensive single-volume resource: Helps readers understand and apply techniques for preventing fatigue and fretting-wear damage due to flow-induced vibration at the design stage Covers components including nuclear reactor internals, nuclear fuels, piping systems, and various types of heat exchangers Features examples of vibration-related failures caused by fatigue or fretting-wear in nuclear and process equipment Includes a detailed overview of state-of-the-art flow-induced vibration technology with an emphasis on two-phase flow-induced vibration Covering all relevant aspects of flow-induced vibration technology, Flow-Induced Vibration Handbook for Nuclear and Process Equipment is required reading for professional mechanical engineers and researchers working in the nuclear, petrochemical, aerospace, and process industries, as well as graduate students in mechanical engineering courses on flow-induced vibration.

This is the 42nd edition of Reference Data Series No. 2, which presents the most recent reactor data available to the IAEA. It contains summarized information as of the end of 2021 on power reactors operating, under construction and shut down as well as performance data on reactors operating in the IAEA Member States. The information is collected through designated national correspondents in the Member States and the data are used to maintain the IAEA's Power Reactor Information System (PRIS).

The United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) established by the General Assembly in 1955 assesses the levels and effects of exposure to ionizing radiation on human health and the environment. This is the first of four volumes of scientific annexes that presents the supporting scientific deliberations for the UNSCEAR 2020/2021 report to the United Nations General Assembly. Annex A "Medical exposure to ionizing radiation" presents a comprehensive global estimate of the frequencies and doses from medical exposure, their distribution and trends in medical categories in the 2009-2018 period. The annex considers four general categories of medical practice using ionizing radiation: (a) diagnostic radiology, including dental radiology and computed tomography, (b) interventional radiology (image-guided interventional procedures), (c) nuclear medicine and (d) radiation therapy.

This 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.

The German abandonment of nuclear power represents one of the most successful popular revolts against technocratic thinking in modern times-the triumph of a dynamic social movement, encompassing a broad swath of West Germans as well as East German dissident circles, over political, economic, and scientific elites. Taking on Technocracy gives a brisk account of this dramatic historical moment, showing how the popularization of scientific knowledge fostered new understandings of technological risk. Combining analyses of social history, popular culture, social movement theory, and histories of science and technology, it offers a compelling narrative of a key episode in the recent history of popular resistance.

This 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.

The International Conference on Research Reactors, held every four years, is one of the IAEA activities supporting countries in addressing the opportunities and challenges related to research reactor programmes. This publication presents a summary and other material from the 2019 conference. The main challenges the research reactor community is facing include the need to ensure regulatory effectiveness, manage the ageing of the facilities, ensure knowledge transfer, and improve utilization programmes and strategic planning. This conference provided a forum for reactor operators, managers, users, regulators, designers and suppliers to exchange best practices and learn from each other, particularly in addressing common issues, challenges and strategies. This resulted in a publication which provides a summary of the conference, the major findings and conclusions of the sessions, and the opening and closing addresses. The accompanying online files include the individual technical papers and presentations.

This 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.