Technical Review of Acceptance Criteria for Pressurized Heavy Water Reactor Fuel, 

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
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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.

Название: Reliability of Advanced High Power, Extended Burnup Pressurized Heavy Water Reactor Fuels: Final Report of a Coordinated Research Project
ISBN: 9201013191 ISBN-13(EAN): 9789201013194
Издательство: Mare Nostrum (Eurospan)
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Описание: The rapid pace of technological change constantly gives rise to new ethical dilemmas. This provides a practical introduction for engineering students that emphasizes ethical decision-making. The authors situate engineering ethics in the wider context of business and environmental ethics and guide students through case studies emphasizing value conflicts often encountered in engineering.

Автор: Riznic, Jovica
Название: Pressurized Heavy Water Reactors,7
ISBN: 0128220546 ISBN-13(EAN): 9780128220542
Издательство: Elsevier Science
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Цена: 176290.00 T
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Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs.

Including contemporary capabilities and challenges of nuclear technology, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties.

Автор: Riznic, Jovica
Название: Pressurized Heavy Water Reactors,8
ISBN: 032385382X ISBN-13(EAN): 9780323853828
Издательство: Elsevier Science
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Pressurized Heavy Water Reactors: Atucha-II, the eighth volume in the JSME Series on Thermal and Nuclear Power Generation, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents a close analysis of the Atucha reactor, covering reactor physics, aging management of major components, and the role of codes in PHWR and Nuclear Regulation and Licensing. Including contemporary capabilities and challenges of nuclear technology, the book offers solutions and advice on common problems faced, guiding the reader through safe and approved processes that will help them reach suitable solutions.

Professionals involved in lifecycle assessments and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, design and licensing.

Название: Applicability of Design Safety Requirements to Small Modular Reactor Technologies Intended for Near Term Deployment: Light Water Reactors High Temperature Gas Cooled Reactors
ISBN: 9201308205 ISBN-13(EAN): 9789201308207
Издательство: Mare Nostrum (Eurospan)
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Цена: 17550.00 T
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Описание: IAEA Member States have expressed relevant interest in the development and deployment of small and medium-sized or modular reactors (SMRs) to help cover their energy needs in the coming decades. SMR designs may include technological characteristics that differ significantly from those of the large nuclear power plants that are commercially available. Those SMR characteristics can represent a challenge when the existing design requirements, as established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) Safety of Nuclear Power Plants: Design, are intended to be applied to SMRs. This publication focuses on the engineering judgement necessary to apply each of the design requirements in SSR-2/1 (Rev. 1), and also the entire set of requirements, to light water cooled and high temperature gas cooled SMRs. The publication includes the common ground reached by representatives from regulatory bodies, technical and scientific support organizations (TSOs) and SMR design organizations regarding the applicability of the design requirements to both SMR technologies. The insights provided are also intended to contribute to motivating further progress in the harmonization of national and international views on safety approaches for SMR technologies. This publication is intended for use by organizations dealing with nuclear power plant design or operation, and by regulatory bodies and TSOs, particularly from countries that are initiating or enlarging nuclear power programmes that include SMR units.

Автор: Rebak, Raul B.
Название: Accident-Tolerant Materials For Light Water Reactor Fuels
ISBN: 0128175036 ISBN-13(EAN): 9780128175033
Издательство: Elsevier Science
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Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an accident tolerant fuel is and the benefits and detriments of each concept. The book begins with an introduction to nuclear power as a renewable energy source and the current materials being utilized in light water reactors. It then moves on to discuss the recent advancements being made in accident tolerant fuels, reviewing the specific materials, their fabrication and implementation, environmental resistance, irradiation behavior, and licensing requirements. The book concludes with a look to the future of new power generation technologies. It is written for scientists and engineers working in the nuclear power industry and is the first comprehensive work on this topic.

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)
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Цена: 45270.00 T
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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: 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: Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data
ISBN: 9201337108 ISBN-13(EAN): 9789201337108
Издательство: Mare Nostrum (Eurospan)
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Цена: 16630.00 T
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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: Ravindra Munje; Balasaheb Patre; Akhilanand Tiwari
Название: Investigation of Spatial Control Strategies with Application to Advanced Heavy Water Reactor
ISBN: 9811030138 ISBN-13(EAN): 9789811030130
Издательство: Springer
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Цена: 102480.00 T
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Описание: Further, it introduces a nonlinear model characterizing important thermal hydraulics parameters of AHWR and integrates it into the neutronics model to obtain a coupled neutronics-thermal hydraulics model of AHWR.

Название: Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
ISBN: 920114413X ISBN-13(EAN): 9789201144133
Издательство: Mare Nostrum (Eurospan)
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Цена: 16630.00 T
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Описание: Reports on the results of an IAEA coordinated research project on benchmarking severe accident computer codes for heavy water reactor applications. This summary report provides a comparison of key results for the selected Station Blackout scenario and concludes with lessons learned and recommendations for future activities.

Автор: Ravindra Munje; Balasaheb Patre; Akhilanand Tiwari
Название: Investigation of Spatial Control Strategies with Application to Advanced Heavy Water Reactor
ISBN: 9811097631 ISBN-13(EAN): 9789811097638
Издательство: Springer
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Цена: 93160.00 T
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Описание: This book examines the different spatial control techniques for regulation of spatial power distribution in advanced heavy water reactors (AHWR). It begins with a review of the literature pertinent to the modeling and control of large reactors. It also offers a nodal-core model based on finite difference approximation since the AHWR core is considered to be divided into 17 relatively large nodes. Further, it introduces a nonlinear model characterizing important thermal hydraulics parameters of AHWR and integrates it into the neutronics model to obtain a coupled neutronics-thermal hydraulics model of AHWR. The book also presents a vectorized nonlinear model of AHWR and implements it in MATLAB/Simulink environment. The model of the reactor is then linearized at the rated power and put into standard state variable form. It is characterized by 90 states, 5 inputs and 18 outputs. Lastly, it discusses control techniques for a nonlinear model of AHWR. This book will prove to be a valuable resource for professional engineers and implementation specialists, researchers and students.