Numerical Benchmarks for Multiphysics Simulation of Pressurized Heavy Water Reactor Transients, 

Название: Technical Review of Acceptance Criteria for Pressurized Heavy Water Reactor Fuel
ISBN: 9201168209 ISBN-13(EAN): 9789201168207
Издательство: Mare Nostrum (Eurospan)
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Описание: Presents a collection of current practices of fuel acceptance criteria used in States with operating pressurized heavy water reactors (PHWRs) and provides the technical justification available for such criteria conditions.

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.

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.

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.

Автор: Riznic, Jovica
Название: Pressurized Heavy Water Reactors,7
ISBN: 0128220546 ISBN-13(EAN): 9780128220542
Издательство: Elsevier Science
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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: Pamela Lassahn
Название: Anticipated and Abnormal Plant Transients in Light Water Reactors
ISBN: 1468448013 ISBN-13(EAN): 9781468448016
Издательство: Springer
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Цена: 113190.00 T
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Описание: The plant transient topic area is a multidisciplinary subject involving not only the nuclear, fluid flow, and heat transfer technologies, but also the synergistics of these with the reactor control systems, the safety s;,"stems, operator actions, maintenance and even management and the economic considerations of a given plant.

Название: Benchmarks of Fuel Burnup and Material Activation Computational Tools Against Experimental Data for Research Reactors
ISBN: 9201013221 ISBN-13(EAN): 9789201013224
Издательство: Mare Nostrum (Eurospan)
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Описание: Provides the final consolidated results of an IAEA coordinated research project (CRP). The publication comprises the benchmark studies, details of the calculations in the annexes and individual reports of the CRP participants in the online supplementary files.

Название: Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of the HTTR and HTR-10
ISBN: 9201162030 ISBN-13(EAN): 9789201162038
Издательство: Mare Nostrum (Eurospan)
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Описание: High-temperature gas cooled reactor (HTGR) designs present special computational challenges related to their core physics and thermal-hydraulic characteristics. Neutron streaming and double heterogeneities are examples of the core physics challenges, while porous gas flow in a high-temperature ceramic core with the interaction of conduction, convection and radiation regimes characterize thermal-hydraulic challenges. In an effort to address such potential calculation uncertainties, computational results made by various international institutes are reported and code-to-code and code-to-experiment comparisons are made. The experimental data are mainly related to the initial testing of the Japanese HTTR and the Chinese HTR-10. Both are high-temperature gas cooled test reactors. The work is part of an IAEA Co-ordinated Research Project (CRP) with the participation of ten international institutes.

Автор: Iaea
Название: Benchmarking of computational fluid dynamics codes for reactor vessel design
ISBN: 9201074204 ISBN-13(EAN): 9789201074201
Издательство: Mare Nostrum (Eurospan)
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Описание: This publication provides a description of the Rossendorf coolant mixing (ROCOM) test facility, used to provide benchmark experiments related to the phenomena of pressurized thermal shock (PTS) and boron dilution, the calculation results using computational fluid dynamics (CFD) codes and methods, and the conclusions drawn from comparison of CFD results with experimental measurements. The aim of this benchmarking was to provide CFD practitioners with two high quality datasets of relevance to reactor transients inside a pressurized water reactor pressure vessel with different configurations and involving mixed convection, stratification, jet impingement and unsteady (inverse) plumes. The focus of the benchmarking was on the three main regions of the cold domain of the primary circuit, i.e. the cold leg, the downcomer and the core entry region. The work was carried out within the framework of an IAEA coordinated research project on application of computational fluid dynamics codes to nuclear power plant design.

Название: Technical Insights from Benchmarking Different Methods for Predicting Pipe Failure Rates in Water Cooled Reactors
ISBN: 9201411219 ISBN-13(EAN): 9789201411211
Издательство: Mare Nostrum (Eurospan)
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Описание: Presents the outcome of an IAEA coordinated research project (CRP) on methodologies for assessing pipe failure rates in advanced water cooled reactors. The goal of the CRP was to provide Member States with a strong technical basis for establishing nuclear power plant piping reliability parameters.

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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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: International Atomic Energy Agency
Название: Benchmark analysis of numerical models for tsunami simulation
ISBN: 9201284217 ISBN-13(EAN): 9789201284211
Издательство: Mare Nostrum (Eurospan)
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Описание: In recent years there has been an evolution in numerical models used to compute tsunami propagation and run-up. Many models currently available offer a wide array of choices to the users. In parallel with the development of such numerical models, it is important that the user only applies the verified and validated numerical models that have undergone a benchmark analysis. This publication provides information and benchmark problems to enable engineers and regulators to select the most appropriate tsunami analysis software and modelling for the evaluation of tsunami hazards for nuclear installations to ensure their safety against those events. In addition, the benchmark problems will enable such users to become familiar with the limitations of the tsunami analysis modelling available in research and commercial software.