Behaviour of spent power reactor fuel during storage,
Название: Management of Spent Fuel from Nuclear Power Reactors: An Integrated Approach to the Back End of the Fuel Cycle ISBN: 9201018193 ISBN-13(EAN): 9789201018199 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 25870.00 T Наличие на складе: Нет в наличии. Описание: These proceedings present the outcome of the 2015 IAEA international conference on the management of spent fuel from nuclear power reactors. Achievements and lessons learned in connection with the back end of the nuclear fuel cycle and associated challenges were shared and reviewed. The conference was organized around seven themes, covering spent fuel management strategies; status and challenges in an integrated approach; safety aspects of spent fuel management; ageing management programmes; storage options in support of an integrated approach; impact of the front end of the nuclear fuel cycle on the back end; and research and development required to deliver an integrated approach. Key goals were to raise awareness on how developments in power generation and availability of disposal can impact on spent fuel management, to evaluate the advances in management of spent fuel from power reactors since the inception of IAEA conferences on this topic, and to identify pending issues and anticipated future challenges. The main ideas and messages expressed and discussed at the conference are presented in the opening addresses, the session summaries and the President’s summary and conclusions of the conference. The attached CD contains the papers and posters presented at the conference.
Название: Technical Approach to Probabilistic Safety Assessment for Multiple Reactor Units ISBN: 9201026188 ISBN-13(EAN): 9789201026187 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 17550.00 T Наличие на складе: Нет в наличии. Описание: The technical approach described in this publication builds on the use of a single unit probabilistic safety assessment (PSA) and identifies considerations that are needed from the multi-unit perspective. This is the first attempt to expand the current PSA process to take account of multi-unit issues, and has been done by distilling lessons learned from the Fukushima Daiichi accident and other multi-unit events, and by reviewing previous PSAs and supporting research that have addressed the risks of multi-unit accidents. The publication provides a roadmap and methodology for performing a multi-unit PSA, proposes a set of site level risk metrics, and presents examples of approaches to resolve specific issues.
Название: Management and Storage of Research Reactor Spent Nuclear Fuel: Proceedings of a Technical Meeting Held in Thurso, United Kingdom, 19–22 October 2009 ISBN: 9201382103 ISBN-13(EAN): 9789201382108 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 45270.00 T Наличие на складе: Невозможна поставка. Описание: Presents the proceedings of a technical meeting to discuss good practices for the management and storage of research reactor spent fuel. The information provided on these issues will be of interest to managers of research reactors and research reactor spent nuclear fuel facilities.
Название: Management of Spent Fuel from Nuclear Power Reactors: Proceedings of an International Conference Held in Vienna, Austria, 31 May–4 June 2010 ISBN: 9201037147 ISBN-13(EAN): 9789201037145 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 38450.00 T Наличие на складе: Невозможна поставка. Описание: This publication presents the proceedings of an international conference on spent fuel management organized by the IAEA in cooperation with the NEA of the OECD. The conference covered a broad range of topics from national strategies through safety and regulatory aspects, transport, technical innovation, fuel and material behaviour, operational experience with storage, new fuel and reprocessing developments, and long term storage and disposal. The conference also featured two round table discussion sessions covering regulatory frameworks and stakeholder issues. The proceedings include the opening presentations and the President’s summary and the conclusions of the conference. A CD-ROM with contributed papers accompanies the publication.
Название: Design, Manufacturing and Irradiation Behaviour of Fast Reactor Fuel: Proceedings of a Technical Meeting held in Obninsk, Russian Federation, 30 May–3 June 2011 ISBN: 9201865104 ISBN-13(EAN): 9789201865106 Издательство: Mare Nostrum (Eurospan) Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: This publication presents the proceedings of a technical meeting organized in order to share knowledge and practical experience on the improvement and innovation of fuels for fast reactors. The objective of the meeting was to provide an overview of the status of the design, manufacture and irradiation behaviour of fast reactor fuel. Scientists and engineers from different fields discussed critical issues, with the aim of supporting efforts relating to the design and manufacture of nuclear fuels for the existing and next generation of fast reactors, as well as the optimization of future irradiation experiments.
Название: Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies: Operational Behaviour ISBN: 9201275102 ISBN-13(EAN): 9789201275103 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 28650.00 T Наличие на складе: Невозможна поставка. Описание: Summarizes the findings of several IAEA meetings on fast reactor materials and provides a review of historically available and new information on the properties, fabrication technologies and irradiation behaviour of stainless steel structural materials for liquid metal cooled fast reactor (LMFR) fuel assemblies.
Название: Advances in High Temperature Gas Cooled Reactor Fuel Technology ISBN: 9201868103 ISBN-13(EAN): 9789201868107 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments.
Название: Quality and Reliability Aspects in Nuclear Power Reactor Fuel Engineering ISBN: 9201031149 ISBN-13(EAN): 9789201031143 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 38450.00 T Наличие на складе: Невозможна поставка. Описание: In order to decrease costs and increase competitiveness, nuclear utilities use more challenging operational conditions, longer fuel cycles and higher burnups, which require modifications in fuel designs and materials. Different aspects of quality assurance and control, as well as analysis of fuel performance have been considered in a number of specialized publications. The present publication provides a concise but comprehensive overview of all interconnected quality and reliability issues in fuel fabrication, design and operation. It jointly tackles technical, safety and organizational aspects, and contains examples of state of the art developments and good practices of coordinated work of fuel designers, vendors and reactor operators.
Название: Advances in High Temperature Gas Cooled Reactor Fuel Technology ISBN: 9201253109 ISBN-13(EAN): 9789201253101 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments.
Название: Pressurized Heavy Water Reactor Fuel: Integrity, Performance and Advanced Concepts: Proceedings of the Technical Meetings Held in Bucharest, 24–27 September 2012, and in Mumbai, 8–11April 2013 ISBN: 9201584148 ISBN-13(EAN): 9789201584144 Издательство: Mare Nostrum (Eurospan) Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: This publication is the proceedings of two technical meetings held in 2012 and 2013 on fuel integrity, performances and advanced fuels for pressurized heavy water reactors (PHWRs). The objective of these meetings was to update the information on the performances of PHWR fuels, the status and trends in the use of advanced fuels in PHWRs and the technical readiness for the deployment of such fuel cycles in these types of reactors.
Advances of Computational Fluid Dynamics in Nuclear Reactor Design and SafetyAssessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors.
Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants.
Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors
Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future
Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization
Название: Research Reactor Benchmarking Database: Facility Specification and Experimental Data ISBN: 9201517149 ISBN-13(EAN): 9789201517142 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 37620.00 T Наличие на складе: Невозможна поставка. Описание: This publication contains the facility specifications, experiment descriptions, and corresponding experimental data for nine different research reactors covering a wide range of research reactor types, power levels and experimental configurations. Each data set was prepared in order to serve as a stand-alone resource of well documented experimental data, which can subsequently be used in benchmarking and validation of the neutronic and thermohydraulic computational methods and tools employed for improved utilization, operation and safety analysis of research reactors.
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