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.

Starting from basic principles, this book describes the rapidly growing field of modern semiconductor detectors used for energy and position measurement radiation. The author, whose own contributions to these developments have been significant, explains the working principles of semiconductor radiation detectors in an intuitive way. Broad coverage is also given to electronic signal readout and to the subject of radiation damage.

The Book represents a collection of papers prepared for and presented by specialists of seven concerned countries in the fourth Advanced Research Workshop (ARW), Moscow, September 22-24, 2004, sponsored and organized within the framework of the NATO-Russia partnership.Similar to the three previous publications, which collected the materials of the NATO-Russia ARWs held in Moscow in 1995, 1997 and 2002, the fourth book of the same series also addresses a very important challenge of the present - complex decommissioning of the taken-out-of-service nuclear-powered vessels and environmental rehabilitation of the centers of basing and everyday running of different-type nuclear vessels. The fourth book especially focuses on the scientific and technical problems of management of naval spent nuclear fuel and radioactive waste.

Countries around the world are spending up to $500 billion per year on subsidising fossil fuel consumption. By some estimates, the G20 countries alone are spending around another $450 billion on subsidising fossil fuel production. In addition, the indirect social welfare costs of these subsidies have been shown to be substantial - for instance due to air pollution, road congestion, climate change, and economic inefficiency, to name a few. Considering these numbers, there is no doubt that fossil fuel subsidies cause severe economic distortions that compromise countries' prospects of achieving equitable and sustainable development. This book provides a guide to the complex challenge of designing, assessing, and implementing effective fossil fuel subsidy reforms. It shows that subsidy reform requires a careful balancing of complex economic and political trade-offs, as well as measures to mitigate adverse effects on vulnerable households and to assist firms with implementing efficiency enhancing measures. Going beyond the purely fiscal perspective, this book emphasises that smart subsidy reforms can contribute to all three dimensions of sustainable development - environment, society, and economy. Over the course of eight chapters, this book considers a wide range of agents and stakeholders, markets, and policy measures in order to distil the key principles of designing effective fossil fuel subsidy reforms. This book will be of great relevance to scholars and policy makers with an interest in energy economics and policy, climate change policy, and sustainable development more broadly.

In Volume 1, A Monte Carlo Primer - A Practical Approach to Radiation Transport (the "Primer"), we attempt to provide a simple, convenient, and step-by-step approach to the development, basic understanding, and use of Monte Carlo methods in radiation transport. Using the PC, the Primer begins by developing basic Monte Carlo codes to solve simple transport problems, then introduces a teaching tool, the Probabilistic Framework Code (PFC), as a standard platform for assembling, testing, and executing the various Monte Carlo techniques that are presented. This second volume attempts to continue this approach by using both custom Monte Carlo codes and PFC to apply the concepts explained in the Primer to obtain solutions to the exercises given at the end of each chapter in the Primer. A relatively modest number of exercises is included in the Primer. Some ambiguity is left in the statement of many of the exercises because the intent is not to have the user write a particular, uniquely correct piece of coding that produces a specific number as a result, but rather to encourage the user to think about the problems and develop further the concepts explained in the text. Because in most cases there is more than one way to solve a Monte Carlo transport problem, we believe that working with the concepts illustrated by the exercises is more important than obtaining anyone particular solution.

The Russian NATO Advanced Research Workshop on "Scientific Problems and Unresolved Issues Remaining in the Decommissioning of Nuclear Powered Vessels and in the Environmental Remediation ofTheir Supporting Infrastructure," was held in Moscow, Russia at the Presidium of the Russian Academy of Sciences on April 22-24, 2002. This was the third in this series of North Atlantic Treaty Organization (NATO) sponsored workshops in Moscow on nuclear vessel decommissioning. The first one was in June 1995 and served to focus international attention on the problems of nuclear vessel decommissioning in Russia and elsewhere. The second one was in November 1997 and it focused on the risks associated with nuclear vessel decommissioning. Attendance at the current workshop was approximately 100 with participants form Russia, United States, Norway, France, Denmark, Germany, Japan, Korea, NATO, and the European Union. The Workshop was sponsored and funded by the Security-Related Civil Science and Technology Program of the Scientific and Environmental Affairs Division ofNATO. Within Russia, the Workshop was sponsored and supported by the Russian Academy of Sciences, Minatom of Russia, Rossudostroenie, Ministry of Industry and Science of Russia, and the Russian Navy. Within the U.S., the Workshop was supported by the U.S. Department of Energy. The sponsorship and support of all of the above organizations are gratefully acknowledged.

In September, 1999, with the generous support of NATO, scientists from 18 different nations gathered in Katsiveli, Yalta, Ukraine at the NATO Advanced Research Workshop on Hydrogen Materials Science and Chemistry of Metal Hydrides to present their research and to discuss world energy problems and possible solutions, interactions of hydrogen with materials, the role of hydrogen in materials science, and the chemistry of metal hydrides. High level and highly professional presentations were accompanied by a great deal of discussion and debate of the issues from both fundamental and global perspectives. The result was a large number of new collaborations, new directions, and better understanding of energy and materials issues. The research presented at this meeting can be found in this volume. These papers range from global perspectives such as the new vision of energy and how hydrogen fits into that future, to reviews such as a look at nickel hydride over the last 40 years, to very specific current research. A large number of papers are included on hydrogen and materials. These papers include articles on properties such as superconductivity, diffusion EMF, magnetic properties, physico chemical properties, phase composition, and permeability as a result of the interaction with or incorporation of hydrogen. Also included are papers discussing the use of hydrogen as a processing or alloying agent. The use of hydrogen in the synthesis of battery electrode materials, composite materials, and alloys is also presented."

A compendium representing the current state of the art in the modelling, simulation and physics of the interaction of hydrogen and helium with plasma facing materials in fusion reactors. This is the topic that will determine the success of the production of energy by future Tokamak reactors and it is here discussed by the world's experts. Topics covered are recycling of hydrogen isotopes; wall fuelling and wall pumping; active control of hydrogen recycling; hydrogen and helium behaviour in solids and liquid metals; and databases for recycling.

For over 60 years, scientists and engineers have been trying to crack a seemingly intractable problem: how to build practical devices that exploit nuclear fusion. Access to electricity has facilitated a standard of living that was previously unimaginable, but as the world’s population grows and developing nations increasingly reap the benefits of electrification, we face a serious global problem: burning fossil fuels currently produces about eighty percent of the world's energy, but it produces a greenhouse effect that traps outgoing infrared radiation and warms the planet, risking dire environmental consequences unless we reduce our fossil fuel consumption to near zero in the coming decades. Nuclear fusion, the energy-producing process in the sun and stars, could provide the answer: if it can be successfully harnessed here on Earth, it will produce electricity with near-zero CO2 byproduct by using the nuclei in water as its main fuel. The principles behind fusion are understood, but the technology is far from being fully realized, and governments, universities, and venture capitalists are pumping vast amounts of money into many ideas, some highly speculative, that could lead to functioning fusion reactors. This book puts all of these attempts together in one place, providing clear explanations for readers who are interested in new energy technologies, including those with no formal training in science or engineering. For each of the many approaches to fusion, the reader will learn who pioneered the approach, how the concept works in plain English, how experimental tests were engineered, the future prospects, and comparison with other approaches. From long-established fusion technologies to emerging and exotic methods, the reader will learn all about the idea that could eventually constitute the single greatest engineering advance in human history.

LESLIE J. JARDINE Lmvrence Livermore National LaboratOlY Livermore, CA 94551 U. S. A. The Advanced Research Workshop (ARW) on Nuc1ear Materials Safety held lune 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 V. S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuc1ear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuc1ear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, inc1uding vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This AR W completed discussions by experts of the nuc1ear materials safety topics that were not covered in the previous, companion ARW on Nuc1ear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuc1ear material aspects of the storage and disposition operations required for excess HEV and plutonium (see Fig. 1, Opening Remarks).

A great number of nuclear submarines are due to be decommissioned before 2000. The political decisions surrounding the disposal of nuclear compartments, radioactive wastes and spent fuel differ appreciably between the countries that own the boats. The decision makers involved thus need help in comparing and assessing alternative options for the decommissioning of their nuclear submarine fleets. The present volume offers such assistance, with its discussions of the risks associated with long-term water storage of the boats, radioactive and chemical contamination, spent fuel and waste management, and handling and recycling reactor compartments.

The "VOLGA" conferences, hosted in odd-numbered years by the Department of Theoretical and Experimental Reactor Physics of the Moscow Engineering Physics Institute (MEPhI), are some of the most prestigious technical meetings held in Russia. Traditionally, these conferences present the opportunity for reactor physicists from around the world to gather at MEPhI's holiday camp on the banks of the Volga river (near Tver) to exchange ideas and explore innovative concepts related to nuclear power development. In 1997, NATO became involved in the "VOLGA" meetings for the first time by co-sponsoring "VOLGA97" as an advanced research workshop. This workshop broke with tradition a bit in that the venue was moved from MEPhI's holiday camp to a location nearer Moscow. The workshop program was effectively organized in order to cover a broad range of topics relating to the theme of the meeting. Generally, the papers concerned safety related questions associated with utilizing both weapons-grade and reactor-grade plutonium in the nuclear fuel cycle, including facility requirements, licensing issues, proliferation risks, and a variety of advanced concepts for alternative fuel cycles. The program contained a total of ninety-nine papers presented in five days of sessions."

Separation technologies are of crucial importance to the goal of significantly reducing the volume of high-level nuclear waste, thereby reducing the long-term health risks to mankind. International co-operation, including the sharing of concepts and methods, as well as technology transfer, is essential in accelerating research and development in the field.

The writers of this book are all internationally recognised experts in the field of separation technology, well qualified to assess and criticize the current state of separation research as well as to identify future opportunities for the application of separation technologies to the solution of nuclear waste management problems. The major emphases in the book are research opportunities in the utilization of innovative and potentially more efficient and cost effective processes for waste processing/treatment, actinide speciation/separation methods, technological processing, and environmental restoration.

Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students. A complete Solutions Manual is available for professors adopting the text.

Nuclear Reactor Technology Development and Utilization presents the theory and principles of the most common advanced nuclear reactor systems and provides a context for the value and utilization of nuclear power in a variety of applications both inside and outside a traditional nuclear setting. As countries across the globe realize their plans for a sustainable energy future, the need for innovative nuclear reactor design is increasing, and this book will provide a deep understanding of how these technologies can aid in a region's goal for clean and reliable energy. Dr Khan and Dr Nakhabov, alongside their team of expert contributors, discuss a variety of important topics, including nuclear fuel cycles, plant decommissioning and hybrid energy systems, while considering a variety of diverse uses such as nuclear desalination, hydrogen generation and radioisotope production. Knowledge acquired enables the reader to conduct further research in academia and industry, and apply the latest design, development, integration, safety and economic guidance to their work and research.

The present report is a revision of Safety Series No. 75-INSAG-3 (1988), updating the statements made on the objectives and principles of safe design and operation for electricity generating nuclear power plants. It includes the improvements made in the safety of operating nuclear power plants and identifies the principles underlying the best current safety policies to be applied in future plants. It presents INSAG's understanding of the principles underlying the best current safety policies and practices of the nuclear power industry.

Intended primarily for undergraduate chemical-engineering students, this book also includes material which bridges the gap between undergraduate and graduate requirements. The introduction contains a listing of the principal types of reactors employed in the chemical industry, with diagrams and examples of their use. There is then a brief exploration of the concepts employed in later sections for modelling and sizing reactors, followed by basic information on stoichiometry and thermodynamics, and the kinetics of homogeneous and catalyzed reactions. Subsequent chapters are devoted to reactor sizing and modelling in some simple situations, and more detailed coverage of the design and operation of the principal reactor types.

Describes the state-of-the-art techniques and methods involved in the design, operation, preparation and containment of bioreactor systems, taking into account the interrelated effects of variables associated with both upstream and downstream stages of the design process. The importance of the initial steps in the development of a bioprocess, such as strain and media selection, that have an overwhelming influence on all further operations, is emphasized.;This work is intended for biochemical, chemical and bioprocess engineers; biotechnologists; industrial biochemists; micro- and molecular biologists; food scientists; and upper-level undergraduate and graduate students in these disciplines.

Almost 145,000 Americans fled their homes in and around Harrisburg, Pennsylvania, in late March 1979, hoping to save themselves from an invisible enemy: radiation. The reactor at the nearby Three Mile Island nuclear power plant had gone into partial meltdown, and scientists feared an explosion that could spread radiation throughout the eastern United States. Thankfully, the explosion never took place-but the accident left deep scars in the American psyche, all but ending the nation's love affair with nuclear power. In Atoms and Ashes, Serhii Plokhy recounts the dramatic history of Three Mile Island and five more accidents that that have dogged the nuclear industry in its military and civil incarnations: the disastrous fallout caused by the testing of the hydrogen bomb in the Bikini Atoll in 1954; the Kyshtym nuclear disaster in the USSR, which polluted a good part of the Urals; the Windscale fire, the worst nuclear accident in the UK's history; back to the USSR with Chernobyl, the result of a flawed reactor design leading to the exodus of 350,000 people; and, most recently, Fukushima in Japan, triggered by an earthquake and a tsunami, a disaster on a par with Chernobyl and whose clean-up will not take place in our lifetime. Through the stories of these six terrifying incidents, Plokhy explores the risks of nuclear power, both for military and peaceful purposes, while offering a vivid account of how individuals and governments make decisions under extraordinary circumstances. Today, there are 440 nuclear reactors operating throughout the world, with nuclear power providing 10 percent of global electricity. Yet as the world seeks to reduce carbon emissions to combat climate change, the question arises: Just how safe is nuclear energy?

Biofuel production from waste biomass is increasingly being focused on due to due to several advantages of lignocellulosic biomass, such as availability in abundance from several sources, cost-effectiveness, little competition with food sources, etc. This new volume, Sustainable Biofuel and Biomass: Advances and Impacts, provides an abundance of in-depth information on many types of biofuels from lignocellulosic biomass and also describes biomass sources and their availability for biofuel production. This compiled book features 17 chapters that discuss the different aspects of biofuel production from lignocellulosic biomass. Chapters deal with different types lipase-mediated biofuel production, biohydrogen production from lignocellulosic biomass, triacylglycrol biosynthetic pathways in plants for biofuel applications, the industrial prospects of lignocellulosic bioethanol production, biofuel cell production, potential feedstocks availability for bioethanol production, biofuel production from algal biomass, and many other important topics.

A number of IAEA Member States generate relatively small quantities of radioactive waste and/or disused sealed sources in research or in the application of nuclear techniques in medicine and industry. This publication presents a modular approach to the design of waste processing and storage facilities to address the needs of such Member States with a cost effective and flexible solution that allows easy adjustment to changing needs in terms of capacity and variety of waste streams. The key feature of the publication is the provision of practical guidance to enable the users to determine their waste processing and storage requirements, specify those requirements to allow the procurement of the appropriate processing and storage modules and install and eventually operate those modules.

Nuclear power issues have long been controversial, and often discussed from an inadequate or mistaken understanding. This book is a factual description of the whole fuel cycle, with individual chapters on specific topics from uranium mining, through the manufacture and use of fuel, to recycled products, waste disposal and progress towards a cleared site. Basic principles, environmental radioactivity (both natural and artificial) and provisions for safety are also covered. The level is pitched at a general scientific readership not necessarily familiar with the concepts, and although the viewpoint is naturally pro-nuclear, the aim is to inform rather than persuade. Where options are disputed, as whether used fuel should br reprocessed or discarded directly, both are described. The account is mainly of current practices, with the reasons for them. A final chapter suggests possible changes in the near or more distant future.

This publication summarizes the reviewed information distributed in previous IAEA publications and provides an up to date, overall picture of the management of disused sealed radioactive sources (DSRSs) based upon the current status and trends in this field. It incorporates the most recent experience in source management, including newly developed techniques used for DSRS conditioning and storage. Problems encountered and lessons learned are also highlighted in the publication in order to help avoid the mistakes commonly made in the past in managing disused sources.

The purpose of the Seminar was to provide an international interdisciplinary forum for in-depth discussions on the pros and cons of a denitration step by chemical means in the course of solidification of MAW (medium active waste) and HAW (highly active waste), prior to feeding the calciner or melter. In particular, differences In the volatility of some components and aerosol formation during the vitrification step are of interest. Chemical rather than thermal denitration may have particular merits which could simplify off-gas purification. A reduction in the salt burden of waste solutions, leading to a reduction In the volume of solid waste, may also be achieved. The scientific programme of the Seminar consisted of invited lectures only, given by experts actively engaged in this field of research. The emphasis was on extensive discussions among the partiCipants, with the aim of leading to an objective understanding of the state-of-the-art. The meeting also indentified issues and options for future research.

Leaching tests are conducted according to different standards, pro cedures or recommendations, generally under conditions different from those of the disposal media. Such tests are generally useful for com paring various containment matrices to ensure maximum isolation of radionuclides, and allow waste conditioning processes to be optimized. However, when defining release hypotheses to be taken into consideration for risk analysis, these methods can often lead to hypothesis which are either too optimistic or too pessimistic. The uncertainties basically involve the processes by which containers deteriorate during transport, handling and utlimate storage. Moreover, the interpretation of test results must be more clearly correlated with the known physico-chemical mechanisms involved. In attempting to find an answer to this question, tests have already the recovery been undertaken, including the use of lysimeter devices or of waste materials after several years of storage. The aim of the seminar was to exchange views among experts in characterization, waste management and safety analysis for the purpose of defining the principal actions that could be undertaken or of reorienting ongoing studies in order to limit the uncertainties involved."