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.

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.

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."

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.

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.

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.

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.

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.

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 stepbystep 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.

Since the 1970s, the IAEA has been involved in the analysis of fuel failures in water cooled reactors in normal (nonaccident) operational conditions. This updated version of IAEA Nuclear Energy Series No. NFT2.1 provides information on all aspects of fuel failures in current nuclear power plant operations. It summarizes fuel failure occurrences and their mechanisms and root causes, as well as fuel failure prevention and management in plant operation for 97% of light and heavy water cooled nuclear power units operated worldwide during the period 2006-2015. Data on fuel failures from 1987 to 2006 extracted from three previous IAEA fuel failure reports are included and analysed in the present publication, together with the 2006-2015 fuel failure data, to reveal long term tendencies in fuel performance. In addition to fuel rod leakers, fuel structural damages and other fuel assembly issues are considered in the report.

Recent decades have seen a significant increase in the number of decommissioning projects undertaken globally. Decommissioning technologies have advanced, driven by innovations in digitization and robotics, and the Systematic Approach to Training (SAT) methodology is now being applied to the decommissioning phase of all types of nuclear facilities. This publication provides practical information and examples of good practices in training personnel for decommissioning activities, based on Member States' experience, including guidance on the application of SAT methodology. The increasing use of digital and web?based tools to enhance competence development for implementation of decommissioning programmes is also discussed.

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 third of four volumes of scientific annexes provide the supporting scientific deliberations for the UNSCEAR 2020/2021 report to the General Assembly. Annex C "Biological mechanisms relevant for the inference of cancer risks from low dose and low-dose rate radiation" synthesizes the current knowledge on biological mechanisms of radiation actions at low doses and low-dose-rates, and assesses the implications for understanding the processes of cancer development after exposure to ionizing radiation, and for dose-response relationships of radiation-induced cancers.

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.

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."

35 9.2 TYpical PWR Station Layout 36 9.3 Regions of Highest Radiological Hazard 38 9.4 Decommissioning Scenarios 40 9.5 Existing Structural Features of a PWR which may aid Decommissioning 42 9.6 Structural Features that might be introduced into Future PWR Stations to aid Decommissioning 43 10. REFERENCES 44 11. ACKNOWLEDGEMENTS 45 12. TABLES AND FIGURES 45 APPENDIX A - SUPPLEMENTARY INFORMATION 98 1 1. INTRODUCTION 1.1 This report describes the work carried out by Taylor Woodrow Construction Limited ( WC) in a study aimed at identifying features Which may be incorporated at the design stage of future nuclear power plants to facilitate their eventual decommissioning and, in so dOing, promote economic and radiological benefits at the decommissioning stage. 1.2 For the purposes of this study, decommissioning of a nuclear facility means those measures taken at the end of the facility's operating life to remove it from the site and restore the site to green field conditions, and, While so doing, ensure the continued protection of the public from any residual radioactivity or other potential hazards present in or emanating from the facility. The overall decommissioning process involves eventual dismantling and demolition and may also include, Where possible and appropriate, the intermediate steps of renewal and refurbishing.

Each year billions of dollars are being spent in the area of nuclear power generation to design, construct, manufacture, operate, and maintain various types of systems around the globe. Many times these systems fail due to safety, reliability, human factors, and human error related problems. The main objective of this book is to combine nuclear power plant safety, reliability, human factors, and human error into a single volume for those individuals that work closely during the nuclear power plant design phase, as well as other phases, thus eliminating the need to consult many different and diverse sources in obtaining the desired information.

This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material (2018 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit, shipment after storage and receipt at the final destination of packages. The Advisory Material is not a stand-alone text. It is to be used concurrently as a companion to the IAEA Safety Standards Series No. SSR-6 (Rev. 1) and each paragraph of this guide is numbered correspondingly to the paragraph of the Regulations to which it most directly relates.

A social history of New Mexico's ""Atomic City""Los Alamos, New Mexico, birthplace of the Atomic Age, is the community that revolutionized modern weaponry and science. An ""instant city,"" created in 1943, Los Alamos quickly grew to accommodate six thousand people - scientists and experts who came to work in the top-secret laboratories, others drawn by jobs in support industries, and the families. How these people, as a community, faced both the fevered rush to create an atomic bomb and the intensity of the subsequent cold-war era is the focus of Jon Hunner's fascinating narrative history. Much has been written about scientific developments at Los Alamos, but until this book little has been said about the community that fostered them. Using government records and the personal accounts of early residents, Inventing Los Alamos, traces the evolution of the town during its first fifteen years as home to a national laboratory and documents the town's creation, the lives of the families who lived there, and the impact of this small community on the Atomic Age.

Fundamental of Nuclear Engineering is derived from over 25 years of teaching undergraduate and graduate courses on nuclear engineering. The material has been extensively class tested and provides the most comprehensive textbook and reference on the fundamentals of nuclear engineering. It includes a broad range of important areas in the nuclear engineering field; nuclear and atomic theory; nuclear reactor physics, design, control/dynamics, safety and thermal-hydraulics; nuclear fuel engineering; and health physics/radiation protection. It also includes the latest information that is missing in traditional texts, such as space radiation. The aim of the book is to provide a source for upper level undergraduate and graduate students studying nuclear engineering.

Communication and stakeholder involvement are essential components for a successful disposal programme. Experience around the world suggests that the scientific and technological bases for the safe disposal of radioactive waste are available — disposal solutions exist or can be developed based on established knowledge. However, concerns and opposition among the public and other stakeholders could slow or even prevent the implementation of needed disposal solutions. This publication provides practical guidance on communication and stakeholder involvement for countries embarking on, relaunching or revising a disposal programme. It draws upon past experiences and emphasizes that practical implementation requires adjusting to the evolving context as given by the national, social and political circumstances. The primary intended users of this publication include those working in the field of radioactive waste management in government, regulatory bodies and industry, an especially in organizations responsible to implement solutions for radioactive waste disposal.

This publication provides a global overview of the status of spent fuel and radioactive waste management programmes, inventories, current practices, technologies and trends. It presents information on national arrangements for the management of spent fuel and radioactive waste, and on current waste and spent fuel inventories and their future estimates. Achievements, challenges and trends in the management of spent fuel and radioactive waste are also addressed. This second edition has been developed with a basis of national profiles submitted by Member States, complemented with openly available Joint Convention National Reports. The data reported are fully dependent on the input from the States and by the assumptions made to transform these data into the waste classes defined in IAEA Safety Standards Series No. GSG?1, Classification of Radioactive Waste.