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).

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."

With the end of the Cold War, new opportunities for interaction have opened up between the United States and the countries of the Former Soviet Union. Many of these important initiatives involve the US Department of Energy (DOE) and the Ministry of the Russian Federation for Atomic Energy (MINA TOM). Currently, collaboration is under way which involves reactor safety, the disposition of fissile materials from the weapons program, radioactive waste disposal, and the safety of nuclear warheads. Another fruitful area of interchange resulted from the radiochemical storage tank accident at the site of the Siberian Chemical Compound at Tomsk-7 in 1993. DOE and MINATOM agreed to meet and exchange information about the accident for the purposes of improving safety. A meeting on the Tomsk tank accident was held in Hanford, Washington in 1993, followed by a second meeting in st. Petersburg, Russia in 1994 in which the agenda expanded to include radiochemical processing safety. A third exchange took place in 1995 in Los Alamos, New Mexico, and additional papers were presented on nonreactor nuclear safety. Following a planning session in 1996 in Seattle, Washington, it was decided to hold a fourth technical exchange on the broader subject of nuclear materials safety management. Through a grant from the North Atlantic Treaty Organization (NATO) Disarmament Programme, the meeting took place on March 17- 21, 1997, in Amarillo, Texas as a NATO Advanced Research Workshop (ARW) through grant no. DISRM 961315.

The management and disposal of radioactive wastes are key international issues requiring a sound, fundamental scientific basis to insure public and environmental protection. Large quantities of existing nuclear waste must be treated to encapsulate the radioactivity in a form suitable for disposal. The treatment of this waste, due to its extreme diversity, presents tremendous engineering and scientific challenges. Geologic isolation of transuranic waste is the approach currently proposed by all nuclear countries for its final disposal. To be successful in this endeavor, it is necessary to understand the behavior of plutonium and the other actinides in relevant environmental media. Conceptual models for stored high level waste and waste repository systems present many sCientific difficulties due to their complexity and non-ideality. For example, much of the high level nuclear waste in the US is stored as alkaline concentrated electrolyte materials, where the chemistry of the actinides under such conditions is not well understood. This lack of understanding limits the successful separation and treatment of these wastes. Also, countries such as the US and Germany plan to dispose of actinide bearing wastes in geologic salt deposits. In this case, understanding the speciation and transport properties of actinides in brines is critical for confidence in repository performance and risk assessment activities. Many deep groundwaters underlying existing contaminated sites are also high in ionic strength. Until recently, the scientific basis for describing actinide chemistry in such systems was extremely limited."

This book develops an analysis of the air entrainment processes in free-surface flows. These flows are investigated as homogeneous mixtures with variable density. Several types of air-water free-surface flows are studied: plunging jet flows, open channel flows, and turbulent water jets discharging into air. Experimental observations reported by the author confirm the concept that the air-water mixture behaves as a homogeneous compressible fluid in each case. This book will be of great interest to professionals working in many fields of engineering: chemical, civil, environmental, mechanical, mining, metallurgy, and nuclear.
Key Features
* Covers new information on the air-water flow field: air bubble distributions, air-water velocity profiles, air bubble sizes and bubble-turbulence interactions
* Features new analysis is developed for each flow configuration and compared successfully with model and prototype data
* Includes over 372 references and more than 170 figures with over 60 photographs
* Presents useful information for design engineers and research-and-development scientists who require a better understanding of the fluid mechanics of air-water flows

Nuclear technology in all countries of the world is subject to controls from the International Atomic Energy Agency (IAEA) to prevent its misuse for military purposes. Recently these controls (or "safeguards") have come under criticism for lack of effectiveness, and the IAEA has now elaborated a strengthened safeguards system reaching deep into the domains of national sovereignty. Problems and prospects of the new system are discussed in this book by a team of German and international scholars, practitioners and officials.

This book describes recent technological developments in next generation nuclear reactors that have created renewed interest in nuclear process heat for industrial applications. The author's discussion mirrors the industry's emerging focus on combined cycle Next Generation Nuclear Plants' (NGNP) seemingly natural fit in producing electricity and process heat for hydrogen production. To utilize this process heat, engineers must uncover a thermal device that can transfer the thermal energy from the NGNP to the hydrogen plant in the most performance efficient and cost effective way possible. This book is written around that vital quest, and the author describes the usefulness of the Intermediate Heat Exchanger (IHX) as a possible solution. The option to transfer heat and thermal energy via a single-phase forced convection loop where fluid is mechanically pumped between the heat exchangers at the nuclear and hydrogen plants is presented, and challenges associated with this tactic are discussed. As a second option, heat pipes and thermosyphons, with their ability to transport very large quantities of heat over relatively long distance with small temperature losses, are also examined.

The Advanced Research Workshop on "Nuclear Submarine Decommissioning and Related Problems" was held at the Russian Academy of Sciences in Moscow, Russia on June 19-22, 1995. On June 17 and 18, 1995 some of the workshop participants visited the Zwezdochka Shipyard at Severodvinsk which is a repair and dismantlement facility for Russian nuclear submarines. Attendance at the workshop was approximately 115 with participants from Russia, United States, France, Norway, Canada, Denmark, Sweden, Estonia, and Germany. The workshop was sponsored by the Disarmament Panel of North Atlantic Treaty Organization (NATO) Science Committee. The sponsorship and the financial support of NATO is gratefully acknowledged. The workshop was organized in Russia by the Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE). The efforts of many individuals from IBRAE in producing both a technically challenging workshop and an almost flawless one are also gratefully acknowledged. In addition, the support of the Russian Academy of Sciences, the State Committee of the Russian Federation on Defense Technologies, the Ministry of the Russian Federation on Atomic Energy, the Navy of the Russian Federation, and the United States Department of Energy is acknowledged. xi CURRENT STATUS OF NUCLEAR SUBMARINE DECOMMISSIONING PROBLEMS OF NUCLEAR SUBMARINE DECOMMISSIONING AND RECYCLING N. I. SHUMKOV State Committee for Defense Industry (Goseomoboronprom) Moscow, Russia 1. General Description of the Problem Undoubtedly, the problem of nuclear submarine decommissioning and recycling has been worrying Russian civil and military specialists involved in development, building and operation of submarines for many years.

Purpose ofthe Workshop In the spirit of enhancing developments in science and technology by facilitating international scientific cooperation, the Science Committee of NATO is sponsoring AR W's in several selected priority areas. The objective of this workshop was to discuss what microbial mediated problems have been experienced in the area of nuclear waste management and spent fuel storage. Long term storage of high-level wastes in repositories is just starting in some countries. However, low and medium level wastes have been stored for several decades. In the area of spent fuel interim, storage has been extended at many locations far beyond the intended time. It was a priority of the workshop to examine and discuss what deleterious effects have been observed under these storage conditions or under conditions used in simulated trial tests for predicting material performance under the storage conditions. For example, one chronic problem that was discussed was possibility that microbial influenced corrosion (MIC) could be taking place in the wet storage of spent fuel thereby initiating or accelerating the process of corrosion. Another discussion in the area of waste forms, focused on the presence ofbiofilms which may be breaking down the structure of the waste form and thereby jeopardizing its integrity. The meeting focused on discussing the observations and data collected relating to problems encountered in the storage of these types of wastes, and sharing this information with others that have not monitored their facilities for similar problems.

The issue of nuclear energy excites strong emotions and there are widely differing views as to whether nuclear power can or should make a major contribution to reducing greenhouse gas emissions. With the nuclear issue back on the agenda worldwide, this highly topical collection steers a path through these controversies, presenting the views of proponents of nuclear expansion, examining the challenges that face them and exploring the arguments of those who support alternative approaches.

Nuclear Engineering Mathematical Modeling and Simulation presents the mathematical modeling of neutron diffusion and transport. Aimed at students and early career engineers, this highly practical and visual resource guides the reader through computer simulations using the Monte Carlo Method which can be applied to a variety of applications, including power generation, criticality assemblies, nuclear detection systems, and nuclear medicine to name a few. The book covers optimization in both the traditional deterministic framework of variational methods and the stochastic framework of Monte Carlo methods. Specific sections cover the fundamentals of nuclear physics, computer codes used for neutron and photon radiation transport simulations, applications of analyses and simulations, optimization techniques for both fixed-source and multiplying systems, and various simulations in the medical area where radioisotopes are used in cancer treatment.

In a comprehensive and lucid manner this book presents an understanding of the aging degradation of the major pressurized and boiling water reactor structures and components. The design and fabrication of each structure or component is briefly described followed by information on the associated stressors. Interactions between the design, materials, and various stressors that cause aging degradation are reviewed. In many cases, aging degradation problems have occurred, and the plant experience to date is analysed. The discussions summarize the available aging-related information and are supported with extensive references, including references to U.S. Nuclear Regulatory Commission (USNRC) documents, Electric Power Research Institute reports, U.S. and international conference proceedings and other publications. The book will prove a useful reference for engineers engaged in the operation and life extension of the present generation of nuclear power plants and for those engaged in the design of advanced light water reactors. It will also provide engineering students with insight into the practical materials-related issues associated with the design and operation of nuclear power plants. The work will also serve as a basis for programs to address the new aging-related issues likely to arise as plants get older.

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.

This book focuses on the issue of 'resurgence of nuclear power' and discusses the feasibility of nuclear in the energy mix of Asian economies. It discusses nuclear energy sector in detail in the context of India, a country where currently overseas supply of hydrocarbon fuels plays a major role in meeting the domestic energy needs. The book presents an in-depth analysis of nuclear energy policy as well as regional and global politics surrounding the nuclear industry, and the relevance of nuclear energy from the low-carbon energy perspective. To do so, it explores three different perspectives. To start with, the resurgence of nuclear power is discussed from a global energy perspective to understand whether and how it has been increasingly gaining policy attention among Asian economies. Secondly, it highlights the role of nuclear power in Asia and examines how the collaboration with the global nuclear sector is influencing that role. While the epicentre of nuclear power growth can be seen shifting to the Global East, there is a growing need for strengthening the industry, its legal and regulatory infrastructure and knowledge management. The third perspective focuses on the challenges and opportunities for the nuclear power industry and explores, to what extent the public perception is in favor of nuclear sector in the region. The perceived risks of nuclear power, public perception related to legal and regulatory issues, and concerns regarding land acquisition for nuclear facilities are also discussed. The book contains contributions from specialists in the global energy and nuclear sector, and examines some of the most sought-after topics related to the energy policy studies, especially in the Asian context.

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.

In recent decades, the number of IAEA Member States planning to extend the operation of their nuclear power plants (NPPs) beyond the time frame originally anticipated has steadily increased. These decisions have been influenced by the significant economic advantages offered by the long term operation (LTO) of existing NPPs. This Safety Report complements IAEA Safety Standards Series Nos SSR?2/2 (Rev. 1), Safety of Nuclear Power Plants: Commissioning and Operation, and SSG?48, Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants. It provides information on selected topics from the latter, and specifically, it addresses data collection and record keeping, scope setting for structures, systems and components, plant programmes, corrective action programmes, and documentation of ageing management and LTO assessment. The publication focuses on NPPs throughout their lifetime, including operation beyond the time frame originally established for their operation and decommissioning, while considering the different reactor designs that exist around the world. It is also relevant for facilities for spent fuel storage and radioactive waste management at NPPs. It may also be used as a basis for managing the ageing of other nuclear installations and for radioactive waste 2 management facilities. This Safety Report is intended to provide information for operating organizations but may be also used by regulatory bodies.

The objectives of nuclear criticality safety are to prevent a self-sustained nuclear chain reaction. This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The recommendations address how to ensure subcriticality in systems involving fissile materials during normal operation and during credible abnormal conditions, from initial design through commissioning, operation and decommissioning. This publication also provides recommendations on identification of credible abnormal conditions; performance of criticality safety assessments; verification, benchmarking and validation of calculation methods; safety measures to ensure subcriticality; and management of criticality safety. The guidance and recommendations are applicable to both regulatory bodies and operating organizations.

This book presents an interdisciplinary collection of expert analyses and views of existing verification systems. It provides guidelines and advice for the improvement of those systems as well as for new challenges in the field.

With the resurgence of nuclear power around the world, and the increasingly important role of hydrogen as a clean energy carrier, the utilization of nuclear energy for large-scale hydrogen production will have a key role in a sustainable energy future. Co-generation of both electricity and hydrogen from nuclear plants will become increasingly attractive. It enables load leveling together with renewable energy and storage of electricity in the form of hydrogen, when electricity prices and demand are lowest at off-peak hours of nuclear plants, such as overnight.

"Hydrogen Production from Nuclear Energy "provides an overview of the latest developments and methods of nuclear based hydrogen production, including electrolysis and thermochemical cycles. Particular focus is given to thermochemical water splitting by the copper-chlorine and sulphur-based cycles. Cycle configurations, equipment design, modeling and implementation issues are presented and discussed. The book provides the reader with an overview of the key enabling technologies towards the design and industrialization of hydrogen plants that are co-located and linked with nuclear plants in the future.

The book includes illustrations of technology developments, tables that summarize key features and results, overviews of recent advances and new methods of nuclear hydrogen production. The latest results from leading authorities in the fields will be presented, including efficiencies, costs, equipment design, and modeling.

MOX fuel, a mixture of weapon-grade plutonium and natural or depleted uranium, may be used to deplete a portion of the world's surplus of weapon-grade plutonium. A number of reactors currently operate in Europe with one-third MOX cores, and others are scheduled to begin using MOX fuels in both Europe and Japan in the near future. While Russia has laboratory-scale MOX fabrication facilities, the technology remains under study. No fuels containing plutonium are used in the U.S. The 25 presentations in this book give an impressive overview of MOX technology. The following issues are covered: an up to date report on the disposition of ex-weapons Pu in Russia; an analysis of safety features of MOX fuel configurations of different reactor concepts and their operating and control measures; an exchange of information on the status of MOX utilisation in existing power plants, the fabrication technology of various MOX fuels and their behaviour in practice; a discussion of the typical national approaches by Russia and the western countries to the utilisation of Pu as MOX fuel; an introduction to new ideas, enhancing the disposition option of MOX fuel exploitation and destruction in existing and future advanced reactor systems; and the identification of common research areas where defined tasks can be initiated in cooperative partnership.

This book deals with the specific contact between the fourth state of matter, i.e. plasma, and the first state of matter, i.e. a solid wall, in controlled fusion experiments. A comprehensive analysis of the main processes of plasma-surface interaction is given together with an assessment of the most critical questions within the context of general criteria and operation limits. It also contains a survey on other important aspects in nuclear fusion.