Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors, 

Название: Developments in the Analysis and Management of Combustible Gases in Severe Accidents in Water Cooled Reactors following the Fukushima Daiichi Accident
ISBN: 9201320205 ISBN-13(EAN): 9789201320209
Издательство: Mare Nostrum (Eurospan)
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Цена: 16630.00 T
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Описание: Reviews the current state of technology regarding combustible gas related safety issues in water cooled nuclear reactors, with a specific focus on post-Fukushima Daiichi accident developments. The recent results obtained from experimental and analytical research on hydrogen/combustible gas behaviour are discussed.

Название: Severe Accident Mitigation through Improvements in Filtered Containment Vent Systems and Containment Cooling Strategies for Water Cooled Reactors: Proceedings of a Technical Meeting on Severe Accident Mitigation through Improvements in Filtered Containmen
ISBN: 9201538170 ISBN-13(EAN): 9789201538178
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Цена: 16630.00 T
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Описание: A filtered containment vent system increases the flexibility of plant personnel in coping with unforeseen events. This publication provides the overview of the current status of related activities with the goal to share information between member states on actions, upgrades, and new technologies pertaining to containment cooling and venting.

Название: Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents: Proceedings of a Technical Meeting Held in Chengdu, China, 28 October–1 November 2013
ISBN: 9201586159 ISBN-13(EAN): 9789201586155
Издательство: Mare Nostrum (Eurospan)
Цена: 16630.00 T
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Описание: Nuclear fuel performance and management play an essential role in ensuring safety, competitiveness and public acceptance of nuclear power. Reliability of fuel depends on its proper design, manufacturing, and ability to withstand required normal operational conditions, as well as possible accidents. In-reactor loads on the core materials are extremely high, which defines a need for detailed R&D as a basis for prediction of in-pile fuel behaviour. The Fukushima Daiichi accident has demonstrated the need for adequate analysis of all aspects of fuel performance to prevent a failure, and also to mitigate consequences if an accident occurs. In order to satisfy these demands, new national and international programmes have been launched and advanced modelling codes have been developed. The experience and lessons learned during three sessions of an IAEA technical meeting on modelling of water cooled fuel, including design basis and severe accidents are presented in this publication.

Название: Status of Research and Technology Development for Supercritical Water Cooled Reactors
ISBN: 920101919X ISBN-13(EAN): 9789201019196
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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: Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
ISBN: 920114413X ISBN-13(EAN): 9789201144133
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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.

Название: Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs): Final Report of a Coordinated Research Project
ISBN: 9201023200 ISBN-13(EAN): 9789201023209
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Цена: 16630.00 T
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Описание: Illustrates the state of the art in supercritical water cooled reactor (SCWR) research and development. This is a key supporting publication to researchers and engineers pursuing the development of SCWRs or equipment/components operating at supercritical pressures.

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
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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.

Название: Efficient Water Management in Water Cooled Reactors
ISBN: 9201326106 ISBN-13(EAN): 9789201326102
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Цена: 31410.00 T
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Описание: Discusses current practices for water requirements in nuclear power plants, possible future trends in design of water cooled reactors and the technologies employed. This publication analyses best practices and strategies for lower water withdrawal rates and presents the trade-off between production of electricity and water use and consumption.

Название: Passive Safety Systems in Advanced Water Cooled Reactors (AWCRs): Case Studies: A Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)
ISBN: 9201398107 ISBN-13(EAN): 9789201398109
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Цена: 16630.00 T
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Описание: The final report of the INPRO collaborative project on advanced water cooled reactor (AWCR) case studies in support of passive safety systems. This publication presents case study results on natural circulation and thermal stratification phenomena in selected passive safety systems, as well as findings and conclusions drawn from these case studies.

Название: Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs)
ISBN: 9201076142 ISBN-13(EAN): 9789201076144
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Цена: 16630.00 T
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Описание: In order to develop the supercritical water cooled reactor (SCWR) concept, thermohydraulics of supercritical pressure water is one of the most important areas to be clarified. This publication summarizes the outcome of an IAEA coordinated research project (CRP) on this topic.

Название: Modelling of Transport of Radioactive Substances in the Primary Circuit of Water Cooled Reactors
ISBN: 9201260105 ISBN-13(EAN): 9789201260109
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Описание: Provides information on the modelling of corrosion product behaviour in the primary circuit. This publication reports on the research activities and results from an IAEA coordinated research project in this field and includes details of current best practice.

Название: Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors
ISBN: 9201274106 ISBN-13(EAN): 9789201274106
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Описание: Covers the identification and definition of the thermo-hydraulic phenomena that affect the reliability of passive safety systems; characterization of each phenomenon; integral tests to examine the passive systems and natural circulation; and a methodology for examining passive system reliability.