Nuclear Reactor Technology Assessment for Near Term Deployment,
Автор: D`Auria, Francesco Название: Thermal-Hydraulics of Water Cooled Nuclear Reactors ISBN: 0081006624 ISBN-13(EAN): 9780081006627 Издательство: Elsevier Science Рейтинг: Цена: 297560.00 T Наличие на складе: Поставка под заказ. Описание:
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.
Автор: Azat Solak Название: Nuclear Power: Deployment, Operation & Sustainability ISBN: 1681176122 ISBN-13(EAN): 9781681176123 Издательство: Gazelle Book Services Рейтинг: Цена: 230210.00 T Наличие на складе: Невозможна поставка. Описание: Nuclear power is the use of nuclear reactions that release nuclear energy to generate heat, which most frequently is then used in steam turbines to produce electricity in a nuclear power plant. The term includes nuclear fission, nuclear decay and nuclear fusion. Presently, the nuclear fission of elements in the actinide series of the periodic table produce the vast majority of nuclear energy in the direct service of humankind, with nuclear decay processes, primarily in the form of geothermal energy, and radioisotope thermoelectric generators, in niche uses making up the rest. A nuclear reactor produces and controls the release of energy from splitting the atoms of certain elements. In a nuclear power reactor, the energy released is used as heat to make steam to generate electricity. The principles for using nuclear power to produce electricity are the same for most types of reactor. The energy released from continuous fission of the atoms of the fuel is harnessed as heat in either a gas or water, and is used to produce steam. The steam is used to drive the turbines which produce electricity. Today, reactors derived from designs originally developed for propelling submarines and large naval ships generate about 85% of the worlds nuclear electricity. This book emphasises on successful development, deployment and operation of nuclear power systems worldwide. We are fortunate to live in incredibly exciting and incredibly challenging time. Energy demands due to economic growth and increasing population must be satisfied in a sustainable manner assuring inherent safety, efficiency and no or minimised environmental impact. These considerations are among the reasons that lead to serious interest in deploying nuclear power as a sustainable energy source. Together, catastrophic earthquake and tsunami events in Japan resulted in the nuclear accident that forced us to rethink our methodology to nuclear safety, design requirements and enabled growing interests in advanced nuclear energy systems. The book is intended for students, researchers and practitioners -- who are interested to learn about nuclear power.
Автор: Kulichenko Natalya, Ereira Eleanor Название: Carbon Capture and Storage in Developing Countries: A Perspective on Barriers to Deployment ISBN: 0821396099 ISBN-13(EAN): 9780821396094 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 23100.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Carbon Capture and Storage (CCS) technology could provide a technological bridge for achieving near to midterm GHG emission reduction goals. Integrated CCS technology is still under development and has noteworthy challenges, which would be possible to overcome through the implementation of large-scale demonstration projects. In order to assist developing countries to better understand issues related to potential technology deployment, there is a need to start analyzing various numerous challenges facing CCS within the economic and legal context of developing countries and countries in transition. This report is the first effort of the World Bank Group to contribute to a deeper understanding of (a) the integration of power generation with CCS technologies, as well as their costs; (b) regulatory barriers to the deployment of CCS; and (c) global financing requirements for CCS and applicable project finance structures involving instruments of multilateral development institutions. This report does not provide prescriptive solutions to overcome these barriers, since action must be taken on a country-by-country basis, taking account of different circumstances and national policies. Individual governments should decide their priorities on climate change mitigation and adopt appropriate measures accordingly. The analyses presented in this report may take on added relevance, depending on the future direction of international climate negotiations and domestic legal and policy measures in both developed and developing countries, and how they serve to encourage carbon sequestration. We expect that this report will provide insights for policy makers, stakeholders, private financiers, and donors in meeting the challenges of the deployment of climate change mitigation technologies and CCS in particular.|Bodies move, and they express. There is a body language, and there is a language employed to refer to the body, its parts, and the states of its being. Consciously and unconsciously people judge each other according to body and clothing behavior. What one thinks one expresses is not necessarily how one is seen and judged, and the variety of observations made of the body is diverse. Bodily behavior and interpretations of this behavior face change at frontiers of culture areas, or when cultures meet each other as a result of migration. This book addresses and expands upon these issues. <br><br> <i>Soheila Shahshahani</i> teaches at the Shahid Beheshti University, Teheran, Iran.
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.
Название: Deployment of Hybrid Renewable Energy Systems in Minigrids ISBN: 9292579797 ISBN-13(EAN): 9789292579791 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 18480.00 T Наличие на складе: Невозможна поставка. Описание: This publication highlights the experiences of ADB`s pilot projects to achieve access to electricity and energy efficiency in five developing countries in Asia.
Автор: J.C. Domanus Название: Reference Neutron Radiographs of nuclear reactor fuel / Neutronogrammes de Reference pour le combustible nucl?aire ISBN: 9400963394 ISBN-13(EAN): 9789400963399 Издательство: Springer Рейтинг: Цена: 87070.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: REFERENCE NEUTRON RADIOGRAPHS ON PHOTOGRAPHIC PAPER (SCALE 2:1) AND FILM (SCALE 1:1) 55 PREFACE Although the principles of radiography with neutron beams have been known for some 45 years, their practical application in industry and research is still a rather young field.
Название: Technical Requirements in the Bidding Process for a New Research Reactor ISBN: 9201034148 ISBN-13(EAN): 9789201034144 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 19410.00 T Наличие на складе: Невозможна поставка. Описание: This publication has been developed to assist Member States in the preparation of the technical requirements for the bidding process for a new research reactor. The publication addresses the preparation phase of the bidding process and discusses criteria that may be used in the evaluation of the bids.
Название: Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data ISBN: 9201337108 ISBN-13(EAN): 9789201337108 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Reports on the second international collaborative intercomparison and validation of computer codes for heavy water reactor thermalhydraulic safety analyses. This summary report provides a comparison of the results obtained from six participating countries, utilizing four different computer codes.
Автор: Kenton I Vinson, Rupert E Gilliam Название: Reactor Safety Recommendations: Insights from the Fukushima Dai-Ichi Accident ISBN: 1619426455 ISBN-13(EAN): 9781619426450 Издательство: Nova Science Рейтинг: Цена: 196410.00 T Наличие на складе: Невозможна поставка. Описание: Examines the Near-Term Task Force, which was established in response to Commission direction to conduct a systematic and methodical review of the US Nuclear Regulatory Commission processes and regulations to determine whether the agency should make additional improvements to its regulatory system.
Автор: Vyawahare Название: Fractional-order Modeling of Nuclear Reactor: From Subdiffusive Neutron Transport to Control-oriented Models ISBN: 9811075867 ISBN-13(EAN): 9789811075865 Издательство: Springer Рейтинг: Цена: 93160.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Chapter 1. Fractional Calculus.- Chapter 2. Introduction to Nuclear Reactor Modeling.- Chapter 3. Development and Analysis of Fractional-order Neutron Telegraph Equation.- Chapter 4. Development and Analysis of Fractional-order Point Reactor Kinetics Model.- Chapter 5. Further Developments using Fractional-order Point Reactor Kinetics Model.- Chapter 6. Development and Analysis of Fractional-order Point Reactor Kinetics Models with Reactivity Feedback.- Chapter 7. Development and Analysis of Fractional-order Two-Group Models.
Автор: ASME Название: ASME 2011 Small Modular Reactor International Symposium ISBN: 0791854736 ISBN-13(EAN): 9780791854730 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 190350.00 T Наличие на складе: Невозможна поставка. Описание: Printed collection of 60 full-length, peer-reviewed technical papers.
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