The Halden Man-Machine Laboratory (HAMMLAB) has been at the heart of human factors research at the OECD Halden Reactor Project (HRP). The HRP is sponsored by a group of national organizations, representing nuclear power plant regulators, utilities, and research institutions. The HRP is hosted by the Institute for Energy Technology (IFE) in Halden, Norway. HAMMLAB comprises three full-scale nuclear power plant control room research simulators. The simulator studies performed in HAMMLAB have traditionally been experimental in nature. In a simulator it is possible to study events as they unfold in real time, in a highly realistic operational environment under partially controlled conditions. This means that a wide range of human factors issues, which would be impossible or highly impracticable to study in real-life settings, can thus be addressed in HAMMLAB. Simulator-based Human Factors Studies Across 25 Years celebrates the twenty-fifth anniversary of HAMMLAB by reviewing the human factors studies performed in HAMMLAB across this time-span. A range of human factors issues have been addressed, including: * human-system interfaces; * alarm systems; * computerized procedures; * human-automation interaction; * staffing, teamwork and human reliability. The aim of HAMMLAB studies has always been the same: to generate knowledge for solving current and future challenges in nuclear power plant operation to contribute to safety. The outcomes of HAMMLAB studies have been used to support design and assessment of nuclear power plant control rooms.

In 1969 we feit that the subject of angular correlations in nuclear disintegrat ion had received little special attention at international conferences. It is true that perturbed angular correlations had been discussed at a smalI, highly - specialised meeting at Uppsala in 1963 and that in 1967 certain aspects of perturbed angular correlations had been considered at a conference on hyperfine structure at Asilomar. However, both conferences were very limited in scope from the point of view of a low - energy nuclear physicist. Besides, since these conferences were being held, the field of perturbed ?ngular correlations had received new impetus from the still ex panding application of the implantation of radioactive isotopes in suitable environ ments, from the construction of large superconductive magnets, etc. Meanwhile, the technique of measuring correlations between beta particles and circularly polarized gamma rays had been developed to such a degree that they lent themselves to the in vestigation of beta decay, nuclear structure and charge dependence of nuclear forces. The systematic study of heavy elements had increased the import an ce of alpha-gamma angular correlations which present their own specific problems. Theoretical internal conversion data had become available to such an extent that electron -gamma direct ional correlations became an important tool in the investigation of nuclear structure: in a large number of cases it is more advantageous to study electron -gamma corre lations instead of the commonly measured gamma -gamma directional correlations.

As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes. Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers.

Introduces the reader to engineering magnetohydrodynamics applications and presents a comprehensive guide of how to approach different problems found in this multidisciplinary field. An introduction to engineering magnetohydrodynamics, this brief focuses heavily on the design of thermo-magnetic systems for liquid metals, with emphasis on the design of electromagnetic annular linear induction pumps for space nuclear reactors. Alloy systems that are liquid at room temperature have a high degree of thermal conductivity far superior to ordinary non-metallic liquids. This results in their use for specific heat conducting and dissipation applications. For example, liquid metal-cooled reactors are typically very compact and can be used in space propulsion systems and in fission reactors for planetary exploration. Computer aided engineering (CAE), computational physics and mathematical methods are introduced, as well as manufacturing and testing procedures. An overview on space nuclear systems is also included. This brief is an invaluable tool for design engineers and applied physicists as well as to graduate students in nuclear and mechanical engineering or in applied physics.

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.

Clogging of steam generators in nuclear power plants is a highly sensitive issue in terms of performance and safety and this book proposes a completely novel methodology for diagnosing this phenomenon. It demonstrates real-life industrial applications of this approach to French steam generators and applies the approach to operational data gathered from French nuclear power plants. The book presents a detailed review of in situ diagnosis techniques and assesses existing methodologies for clogging diagnosis, whilst examining their limitations. It also addresses numerical modelling of the dynamic behaviour of steam generators and provides a thorough analysis of statistical methods for sensitivity analysis and dimension reduction. Steam generators are heat exchangers found in nuclear power plants and over time they become increasingly clogged by iron oxides. This clogging then hampers the flow inside steam generators and compromises their mechanical integrity, which hinders performance and safety. This book is intended for nuclear safety specialists, nuclear performance engineers and researchers and postgraduate students working on heat exchanger modeling and computational engineering.

Unlike existing books of nuclear reactor physics, nuclear engineering and nuclear chemical engineering this book covers a complete description and evaluation of nuclear fission power generation. It covers the whole nuclear fuel cycle, from the extraction of natural uranium from ore mines, uranium conversion and enrichment up to the fabrication of fuel elements for the cores of various types of fission reactors. This is followed by the description of the different fuel cycle options and the final storage in nuclear waste repositories. In addition the release of radioactivity under normal and possible accidental conditions is given for all parts of the nuclear fuel cycle and especially for the different fission reactor types.

Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: Atomic economics and management, Atomic safety and reliability, and Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

Stability and Transport in Magnetic Confinement Systems provides an advanced introduction to the fields of stability and transport in tokamaks. It serves as a reference for researchers with its highly-detailed theoretical background, and contains new results in the areas of analytical nonlinear theory of transport using kinetic theory and fluid closure. The use of fluid descriptions for advanced stability and transport problems provide the reader with a better understanding of this topic. In addition, the areas of nonlinear kinetic theory and fluid closure gives the researcher the basic knowledge of a highly relevant area to the present development of transport physics.

When we are looking at proliferation cases, there are a number of lessons - positive and negative - learnt. First, facts reported by the IAEA are essential for the international community in assessing the compliance and risks of possible clandestine activities. Second, the IAEA verification scheme is biting when it fully exercises its verification rights, and when it is provided with the requisite cooperation. Third, when countries face questions raised by the IAEA, those that chose to turn the course and / or cooperated to remove concerns and ambiguities resolved their nuclear dossiers in a satisfactory manner and fairly swiftly. Fourth, when states adopt the course of confrontation, as are currently the cases with Iran, Syria and North Korea, the situation becomes more complicated and more difficult to resolve. Fifth, dragging non-compliance and challenging of the authority of the United Nations Security Council and the IAEA Board of Governors erodes the international non-proliferation regime. This book addresses two proliferation cases, Iran and North Korea providing extensive snapshots on the currently known nuclear programs, and analyses failures and weaknesses of past verification activities, and makes innovative suggestions for ways forward.

Advances in Light Water Reactor Technologies focuses on the design and analysis of advanced nuclear power reactors. This volume provides readers with thorough descriptions of the general characteristics of various advanced light water reactors currently being developed worldwide. Safety, design, development and maintenance of these reactors is the main focus, with key technologies like full MOX core design, next-generation digital I&C systems and seismic design and evaluation described at length. This book is ideal for researchers and engineers working in nuclear power that are interested in learning the fundamentals of advanced light water plants.

Safety of VVER-440 Reactors endeavours to promote an increase in the safety of VVER-440 nuclear reactors via the improvement of fission products limitation systems and the implementation of special non-destructive spectroscopic methods for materials testing. All theoretical and experimental studies performed the by author over the last 25 years have been undertaken with the aim of improving VVER-440 defence in depth, which is one of the most important principle for ensuring safety in nuclear power plants. Safety of VVER-440 Reactors is focused on the barrier system through which the safety principle is organised: * nuclear fuel matrix; * fuel cladding; * integrity of primary circuit; and * confinement system. All these barriers are described in detail and are compared to European standards. Industrial engineers will find Safety of VVER-440 Reactors a useful guide to the safe operation of nuclear power plants and it is an informative source of information for researchers in both industry and academia. Employees of related governmental and regulatory organisations may also benefit from reading this book.

This book is an outgrowth of courses in plasma physics which I have taught at Kiel University for many years. During this time I have tried to convince my students that plasmas as different as gas dicharges, fusion plasmas and space plasmas can be described in a uni ed way by simple models. The challenge in teaching plasma physics is its apparent complexity. The wealth of plasma phenomena found in so diverse elds makes it quite different from atomic physics, where atomic structure, spectral lines and chemical binding can all be derived from a single equation-the Schroedinger equation. I positively accept the variety of plasmas and refrain from subdividing plasma physics into the traditional, but arti cially separated elds, of hot, cold and space plasmas. This is why I like to confront my students, and the readers of this book, with examples from so many elds. By this approach, I believe, they will be able to become discoverers who can see the commonality between a falling apple and planetary motion. As an experimentalist, I am convinced that plasma physics can be best understood from a bottom-up approach with many illustrating examples that give the students con dence in their understanding of plasma processes. The theoretical framework of plasma physics can then be introduced in several steps of re nement. In the end, the student (or reader) will see that there is something like the Schroedinger equation, namely the Vlasov-Maxwell model of plasmas, from which nearly all phenomena in collisionless plasmas can be derived.

The clamor for non-carbon dioxide emitting energy production has directly impacted on the development of nuclear energy. As new nuclear plants are built, plans and designs are continually being developed to manage the range of challenging requirement and problems that nuclear plants face especially when managing the greatly increased operating temperatures, irradiation doses and extended design life spans. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments provides a comprehensive treatment of the structural materials for nuclear power plants with emphasis on advanced design concepts. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments approaches structural materials with a systemic approach. Important components and materials currently in use as well as those which can be considered in future designs are detailed, whilst the damage mechanisms responsible for plant ageing are discussed and explained. Methodologies for materials characterization, materials modeling and advanced materials testing will be described including design code considerations and non-destructive evaluation concepts. Including models for simple system dynamic problems and knowledge of current nuclear power plants in operation, Materials for Nuclear Plants: From Safe Design to Residual Life Assessments is ideal for students studying postgraduate courses in Nuclear Engineering. Designers on courses for code development, such as ASME or ISO and nuclear authorities will also find this a useful reference.

By drawing together the current theoretical and experimental understanding of the phenomena of delayed hydride cracking (DHC) in zirconium alloys, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking provides a detailed explanation focusing on the properties of hydrogen and hydrides in these alloys. Whilst the emphasis lies on zirconium alloys, the combination of both the empirical and mechanistic approaches creates a solid understanding that can also be applied to other hydride forming metals. This up-to-date reference focuses on documented research surrounding DHC, including current methodologies for design and assessment of the results of periodic in-service inspections of pressure tubes in nuclear reactors. Emphasis is placed on showing how our understanding of DHC is supported by progress in general understanding of such broad fields as the study of hysteresis associated with first order phase transformations, phase relationships in coherent crystalline metallic solids, the physics of point and line defects, diffusion of substitutional and interstitial atoms in crystalline solids, and continuum fracture and solid mechanics. Furthermore, an account of current methodologies is given illustrating how such understanding of hydrogen, hydrides and DHC in zirconium alloys underpins these methodologies for assessments of real life cases in the Canadian nuclear industry. The all-encompassing approach makes The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Component: Delayed Hydride Cracking an ideal reference source for students, researchers and industry professionals alike.

Frontiers in Fusion Research provides a systematic overview of the latest physical principles of fusion and plasma confinement. It is primarily devoted to the principle of magnetic plasma confinement, that has been systematized through 50 years of fusion research. Frontiers in Fusion Research begins with an introduction to the study of plasma, discussing the astronomical birth of hydrogen energy and the beginnings of human attempts to harness the Sun's energy for use on Earth. It moves on to chapters that cover a variety of topics such as: * charged particle motion, * plasma kinetic theory, * wave dynamics, * force equilibrium, and * plasma turbulence. The final part of the book describes the characteristics of fusion as a source of energy and examines the current status of this particular field of research. Anyone with a grasp of basic quantum and analytical mechanics, especially physicists and researchers from a range of different backgrounds, may find Frontiers in Fusion Research an interesting and informative guide to the physics of magnetic confinement.

With the appearance of Volume 3 of our series the review articles them selves can speak for the nature of the series. Our initial aim of charting the field of nuclear physics with some regularity and completeness is, hopefully, beginning to be established. We are greatly indebted to the willing coopera tion of many authors which has kept the series on schedule. By means of the "stream" technique on which our series is based - in which articles emerge from a flow of future articles at the convenience of the authors-the articles appear in this volume without any special coordination of topics. The topics range from the interaction of pions with nuclei to direct reactions in deformed nuclei. There is a great number of additional topics which the series hopes to include. Some of these are indicated by our list of future articles. Some have so far not appeared on our list because the topics have been reviewed re cently in other channels. Much of our series has originated from the sug gestions of our colleagues. We continue to welcome such aid and we continue to need, particularly, more suggestions about experimentalists who might write articles on experimental topics."

This book grew out of projects funded by the Kentucky Human ities Council in 1974 and 1975 and by the Environmental Protec tion Agency in 1976 and 1977. As a result of the generosity of these two agencies, I was able to study the logical, methodological, and ethical assumptions inherent in the decision to utilize nuclear fission for generating electricity. Since both grants gave me the opportunity to survey public policy-making, I discovered that there were critical lacunae in allegedly comprehensive analyses of various energy technologies. Ever since this discovery, one of my goals has been to fill one of these gaps by writing a well-docu men ted study of some neglected social and ethical questions regarding nuclear power. Although many assessments of atomic energy written by en vironmentalists are highly persuasive, they often also are overly emotive and question-begging. Sometimes they employ what seem to be correct ethical conclusions, but they do so largely in an in tuitive, rather than a closely-reasoned, manner. On the other hand, books and reports written by nuclear proponents, often under government contract, almost always ignore the social and ethical aspects of energy decision-making; they focus instead only on a purely scientific assessment of fission generation of electricity. What the energy debate needs, I believe, are more studies which aim at ethical analysis and which avoid unsubstantiated assertions. I hope that these essays are steps in that direction."

Over the last 30 years, reactor safety technology has evolved not so much from a need to recover from accidents or incidents, but primarily from many groups in the nuclear community asking hypo thetical, searching (what if) ~uestions. This ~uestioning has indeed paid off in establishing preventive measures for many types of events and potential accidents. Conditions, such as reactivity excursions, large break, loss of coolant, core melt, and contain ment integrity loss, to name a few, were all at one time topics of protracted discussions on hypothesized events. Historically, many of these have become multiyear, large-scale research programs aimed at resolving the "what ifs. " For the topic of anticipated and abnormal plant transients, how ever, the searching ~uestions and the research were not so prolific until the mid-1970s. At that time, probabilistic risk methodolo gies began to tell us we should change our emphasis in reactor safety research and development and focus more on small pipe breaks and plant transients. Three Mile Island punctuated that message in 1979. The plant transient topic area is a multidisciplinary subject involving not only the nuclear, fluid flow, and heat transfer technologies, but also the synergistics of these with the reactor control systems, the safety s;,"stems, operator actions, maintenance and even management and the economic considerations of a given plant.

Nuclear sites become contaminated with radionuclides due to accidents and activities carried out without due consideration for the environment. Naturally-occurring radioactive materials (NORM) released by industrial processes such as coal power production and fertilizer manufacture may also require clean-up. Environmental remediation and restoration aim to reduce exposure to radiation from contaminated soil or groundwater. This book provides a comprehensive overview of this area. Part 1 provides an introduction to the different types of contaminated site and their characteristics. Part 2 addresses environmental restoration frameworks and processes. Part 3 then reviews different remediation techniques and methods of waste disposal.

This book is devoted to the mathematical optimization theory and modeling techniques that recently have been applied to the problem of controlling the shape and intensity of the power density distribution in the core of large nuclear reactors. The book has been prepared with the following purposes in mind: 1. To provide, in a condensed manner, the background preparation on reactor kinetics required for a comprehensive description of the main problems encountered in designing spatial control systems for nuclear reactor cores. 2. To present the work that has already been done on this subject and provide the basic mathematical tools required for a full understand ing of the different methods proposed in the literature. 3. To stimulate further work in this challenging area by weighting the advantages and disadvantages of the existing techniques and evaluating their effectiveness and applicability. In addition to coverage of the standard topics on the subject of optimal control for distributed parametersystems, the book includes, at amathemati cal level suitable for graduate students in engineering, discussions of con ceptsoffunctional analysis, the representation theory ofgroups, and integral equations. Although these topics constitute a requisite for a full understanding of the new developments in the area of reactor modeling and control, they are seidom treated together in a single book and, when they are, their presenta tion isoften directed to the mathematician.They are thus relatively unknown to the engineering community."

This book is aimed at Health Physicists wishing to gain a better understanding of the principles and practices associated with a light water reactor (LWR) radiation protection program. The role of key program elements is presented in sufficient detail to assist practicing radiation protection professionals in improving and strengthening their current program. Details related to daily operation and discipline areas vital to maintaining an effective LWR radiation protection program are presented. Programmatic areas and functions important in preventing, responding to, and minimizing radiological incidents and the importance of performing effective incident evaluations and investigations are described. Elements that are integral in ensuring continuous program improvements are emphasized throughout the text.