Technical Approach to Probabilistic Safety Assessment for Multiple Reactor Units,
Автор: Zoltan Kovacs Название: Probabilistic Safety Assessment of WWER440 Reactors ISBN: 3319085476 ISBN-13(EAN): 9783319085470 Издательство: Springer Рейтинг: Цена: 121890.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Introduction.- The nuclear power plant with WWER440 reactors.- Level 1 full power PSA.- Level 1 low power and shutdown PSA.- Level 2 PSA.- PSA applications.- Conclusions.
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: Approaches to Safety Evaluation of New and Existing Research Reactor Facilities in Relation to External Events ISBN: 920102617X ISBN-13(EAN): 9789201026170 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 38450.00 T Наличие на складе: Нет в наличии. Описание: This publication provides information and a framework for Member States to conduct realistic safety evaluation for research reactors in terms of external events. The publication provides information with examples on the use of a graded approach, based on the radiological hazard that a facility poses to the environment, public and workers, and takes into account the lessons from the Fukushima accident. This publication supports the development of site specific guidelines for the actual design and safety assessment, and should be used in conjunction with the relevant IAEA Safety Standards. It can also be used as training material for research reactor staff and for a self-assessment of the vulnerability of existing structures to external events.
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.
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
Автор: Zoltan Kovacs Название: Probabilistic Safety Assessment of WWER440 Reactors ISBN: 3319360701 ISBN-13(EAN): 9783319360706 Издательство: Springer Рейтинг: Цена: 95770.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Introduction.- The nuclear power plant with WWER440 reactors.- Level 1 full power PSA.- Level 1 low power and shutdown PSA.- Level 2 PSA.- PSA applications.- Conclusions.
Название: Nuclear Reactor Technology Assessment for Near Term Deployment ISBN: 9201403100 ISBN-13(EAN): 9789201403100 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 27720.00 T Наличие на складе: Невозможна поставка. Описание: Demonstrates how reactor technology assessment is performed and how the process and results of this work enable decision making in nuclear power planning. The approach also provides decision makers with the documentation necessary to support their conclusions.
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: 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: 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.
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.
Название: Design of the Reactor Core for Nuclear Power Plants ISBN: 9201038194 ISBN-13(EAN): 9789201038197 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 39290.00 T Наличие на складе: Невозможна поставка. Описание: The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in SSR-2/1 (Rev. 1) applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical, and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.
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