This publication assists existing and potential stakeholders in the definition of competitive approaches regarding design and deployment of small and medium sized reactors (SMR). It provides a framework for assessment of the investment attractiveness of nuclear power plant projects that adopts small reactor to be deployed in multi-modules and incorporate modularization construction technology. Main chapters detail past experience and future plans in several IAEA Member States and present the suite of models to assist designers and guide potential users on the economic performance and investment attractiveness of SMRs. A framework for the consolidated application of such models is also suggested. The annexes, contributed by Member States, provide in depth descriptions of different assessment models and give examples of their application.

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.

Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. - Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors - Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) - Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes - Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants

This edited book investigates the interrelations of disaster impacts, resilience and security in an urban context. Urban as a term captures megacities, cities, and generally, human settlements, that are characterised by concentration of quantifiable and non-quantifiable subjects, objects and value attributions to them. The scope is to narrow down resilience from an all-encompassing concept to applied ways of scientifically attempting to ‚measure’ this type of disaster related resilience. 28 chapters in this book reflect opportunities and doubts of the disaster risk science community regarding this ‚measurability’. Therefore, examples utilising both quantitative and qualitative approaches are juxtaposed. This book concentrates on features that are distinct characteristics of resilience, how they can be measured and in what sense they are different to vulnerability and risk parameters. Case studies in 11 countries either use a hypothetical pre-event estimation of resilience or are addressing a ‘revealed resilience’ evident and documented after an event. Such information can be helpful to identify benchmarks or margins of impact magnitudes and related recovery times, volumes and qualities of affected populations and infrastructure.

This is Volume 1 of the fully revised second edition. Organized to provide the technical professional with ready access to practical solutions, this revised, three-volume, 2,100-page second edition brings to life essential ASME Codes with authoritative commentary, examples, explanatory text, tables, graphics, references, and annotated bibliographic notes. This new edition has been fully updated to the current 2004 Code, except where specifically noted in the text. Gaining insights from the 78 contributors with professional expertise in the full range of pressure vessel and piping technologies, you find answers to your questions concerning the twelve sections of the ASME Boiler and Pressure Vessel Code, as well as the B31.1 and B31.3 Piping Codes. In addition, you find useful examinations of special topics including rules for accreditation and certification; perspective on cyclic, impact, and dynamic loads; functionality and operability criteria; fluids; pipe vibration; stress intensification factors, stress indices, and flexibility factors; code design and evaluation for cyclic loading; and bolted-flange joints and connections.

This nucleonic gauge manual and directory provides a reference database of nucleonic control systems available to potential users in the fields of exploration, exploitation and processing of natural resources and in the manufacturing industries.

This book was written in the frame of the OPTRES project, which was supported by the European Commission within the framework of the Intelligent Energy for Europe programme. The consortium, consisting of six European partners, analysed the effectiveness as well as the economic efficiency of currently implemented support schemes for renew-able energies in the electricity sector (RES-E) in the enlarged European Union. The analysis gives recommendations for future improvements of the existing RES-E promotion measures. Furthermore the consortium carried out an extensive stakeholder consultation, focussing on the identification of existing market barriers to the development of renewable electricity in the EU. The effectiveness and efficiency of current and future RES-E support schemes were analysed with particular focus on a single European market for renewable electricity products. Current best practices were identified and an assessment made of the (future) costs of RES-E and the relevant support necessary to initiate stable growth. The main barriers to a higher RES-E deployment as perceived by market actors and stakeholders were assessed.

This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.

The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.