10,079 research outputs found

    A framework for the selection of the right nuclear power plant

    Get PDF
    Civil nuclear reactors are used for the production of electrical energy. In the nuclear industry vendors propose several nuclear reactor designs with a size from 35–45 MWe up to 1600–1700 MWe. The choice of the right design is a multidimensional problem since a utility has to include not only financial factors as levelised cost of electricity (LCOE) and internal rate of return (IRR), but also the so called “external factors” like the required spinning reserve, the impact on local industry and the social acceptability. Therefore it is necessary to balance advantages and disadvantages of each design during the entire life cycle of the plant, usually 40–60 years. In the scientific literature there are several techniques for solving this multidimensional problem. Unfortunately it does not seem possible to apply these methodologies as they are, since the problem is too complex and it is difficult to provide consistent and trustworthy expert judgments. This paper fills the gap, proposing a two-step framework to choosing the best nuclear reactor at the pre-feasibility study phase. The paper shows in detail how to use the methodology, comparing the choice of a small-medium reactor (SMR) with a large reactor (LR), characterised, according to the International Atomic Energy Agency (2006), by an electrical output respectively lower and higher than 700 MWe

    INTERIM REPORT IMPROVED METHODS FOR INCORPORATING RISK IN DECISION MAKING

    Get PDF
    This paper reports observations and preliminary investigations in the first phase of a research program covering methodologies for making safety-related decisions. The objective has been to gain insight into NRC perceptions of the value of formal decision methods, their possible applications, and how risk is, or may be, incorporated in decision making. The perception of formal decision making techniques, held by various decision makers, and what may be done to improve them, were explored through interviews with NRC staff. An initial survey of decision making methods, an assessment of the applicability of formal methods vis-a-vis the available information, and a review of methods of incorporating risk and uncertainty have also been conducted

    Review of SMR siting and emergency preparedness

    Get PDF

    Review of SMR siting and emergency preparedness

    Get PDF

    TAMING THE TECHNOLOGICAL TYGERTHE REGULATION OF THE ENVIRONMENTAL EFFECTS OF NUCLEAR POWER PLANTS -A SURVEY OF SOME CONTROVERSIAL ISSUES--PART TWO

    Get PDF
    This article reviews the significance placed on environmental factors in nuclear plant licensing during -the 1960s, first considering the effect of recent legislation and the status of current controversies, and then briefly discussing proposals for legislation and developments that can be expected in the near future

    A review of existing model of no-notice randomized inspection and their potential application to model Pu handling facilities

    Get PDF
    Literature regarding two alternative safeguards concepts--randomization and zones--is reviewed. The concepts were introduced in the early 1980`s to address the need to make safeguards more efficient in the light of the increasing number of facilities under safeguards and a fixed IAEA inspection budget. The paper discusses literature broadly relating these approaches to IAEA needs and objectives, reports from IAEA consultants meetings, reports of field trials, and other technical papers. The review suggests that the approaches have been extensively considered on a theoretical and practical level, and that the safeguards community endorses them on a conceptual level as potentially valid ways of achieving safeguards objectives. Actual utilization of the ideas in safeguards practice has to proceed on a case-by-case basis, but progress is being made

    German Radioactive Waste

    Get PDF
    This book presents the universal issue of radioactive waste management from the perspective of the German legal system, analysing how lawmakers have responded to the problem of nuclear waste over the course of the last seventy years. In this book, Robert Rybski unwraps and explains the perplexing legal and social issues related to radioactive waste. He takes readers through the entire ‘life-cycle’: from the moment that radioactive material is classified as radioactive waste, through to the period of interim storage, and right up to its final disposal. However, this last step in radioactive waste management (that of final disposal) has not yet been achieved in Germany, or anywhere in the world, and has been the subject of hefty public debate for dozens of years. As a result, the book analyses the most recent regulations in place to enable final disposal. This book will be of interest to energy policy experts, academics and professionals who work in the area of nuclear energy

    Operation of Ageing Reactors: Approaches and associated Research in the European Union

    Get PDF
    Plant Life Management (PLiM) of existing nuclear power plants in EU may consider longer term operability. This becomes an option with specific advantages and is under consideration in some Member States. It however unveils number of challenges that are closely related with extending the operational life of structures and components (SC) beyond the established operational time frame at the time they were designed. Safety related aspects of long term operations are obvious; for those SC important to safety that are selected for evaluation it is necessary to demonstrate that they perform the intended safety functions with sufficient safety margins for the entire period of operations. The ageing phenomena needs to be timely and carefully considered, in particular by structural integrity assessment, accident analysis, nuclear power plant ageing assessment and mitigation, systems interactions and risk assessment with related human factor aspects. A broad and effective dissemination of related scientific results is a further objective. The European Union, which sees a large diversity of nuclear plant types, needs a targeted investigation to upgrade knowledge on their objective safety levels. Research activities therefore concentrate on providing the scientific and technical knowledge in relation to safety important issues needed for Community policy support and for helping to enhance nuclear safety in EU and beyond. The European Commission launched within the EURATOM framework programme FP7 a research and support programme related to PLiM issues under progress at Joint Research Centre and involves partners from nuclear industry and Technical Support Organizations through several dedicated networks and projects. This report aims to provide overview of approaches proposed or followed in the USA and in EU countries when longer term operability (LTO) is considered as part of PLiM. A special attention is given to discussing existing regulatory framework available, as well as requirements set for ageing reactors in the corresponding IAEA safety reports and safety guides. A comparison of the US Licence Renewal Rule and Periodic Safety Review as a tool for assessment of Structure, Systems and Components (SSC) for PLiM and LTO is provided too. The present report also discuses several current challenges, and shows some examples how the research is supporting / or can support the safety assessment of ageing nuclear power plants in the European Union.JRC.F.5-Nuclear Reactor Safety Assessmen

    RISK-INFORMED DECISION MAKING AND THE REGULATION OF SMALL MODULAR REACTORS

    Get PDF
    This thesis argues that small modular nuclear reactors (SMRs) can be regulated within the existing Canadian nuclear regulatory framework in light of existing regulatory principles, and that regulatory flexibility and the development of risk management practices will be crucial to accommodate the many challenges associated with their regulation. SMRs are characterized by their small size, modularity and innovative approaches to design. Though advantageous, these novel characteristics introduce uncertain and novel risks that pose challenges to Canada’s risk assessment and risk management practices. The most significant challenge to Canada’s regulators is how SMRs can be safely regulated while imposing regulations that have the appropriate scope, detail and content for each proposed SMR project. This thesis argues that Canada’s risk-informed decision-making process must be bolstered to mitigate the variability and uncertain risks of SMRs. Emphasis is placed on the utilization of the graded approach to accommodate the variability of SMR projects and demonstrate that associated risks meet regulatory objectives. In addition to the graded approach, this thesis proposes risk management approaches that may better utilize uncertainty analyses to ensure that conservative measures are appropriate and that regulatory objectives are satisfied. A method to elicit and assess expert judgment for risk-informed decision-making is proposed to alleviate risk uncertainty and fill gaps in risks. Using these tools, regulators may better accommodate the risks of SMRs without relying on conservative measures to justify the satisfaction of regulatory requirements. This thesis also investigates how type certification of SMR designs can be used to streamline the licensing process to take advantage of their quick construction and installation times. Type certification is the process of certifying a design such that reproductions of that design are assumed to meat regulatory requirements thereby reducing the depth of analysis for subsequent risk assessments of the same reactor. In the type certification process, the assurance that SMR designs can be reproduced by the manufacturer consistently and accurately is a significant concern. The examination of the aviation industry and maritime transport industry yield effective strategies for assuring the reproducibility of SMR designs that may be implemented within Canada

    Process Heat Exchanger Options for the Advanced High Temperature Reactor

    Get PDF
    The work reported herein is a significant intermediate step in reaching the final goal of commercial-scale deployment and usage of molten salt as the heat transport medium for process heat applications. The primary purpose of this study is to aid in the development and selection of the required heat exchanger for power production and process heat application, which would support large-scale deployment
    corecore