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Supercritical Pressure Light Water Cooled Reactors

, and water chemistry. It highlights research on supercritical-pressure light water cooled reactors (SCWRs), one of the Generation IV reactors;

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Safety of Sodium-Cooled Fast Reactors

-cooled fast reactors. Knowledge provided is also useful for those who are engaging in severe accident analysis for lead-cooled fast reactors and;

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

of severe accident analysis codes and recommends areas for research and development. The information is detailed in terms of major findings,;

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Review of Fuel Failures in Water Cooled Reactors (2006-2015)

Since the 1970's, the IAEA has been involved in the analysis of fuel failures in water cooled reactors in normal (non-accident) operational;

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Thermal-Hydraulics of Water Cooled Nuclear Reactors

of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the;

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Super Light Water Reactors and Super Fast Reactors

gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors;

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Super Light Water Reactors and Super Fast Reactors

gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors;

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Nuclear Reactor Design

core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core;

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Accident-Tolerant Materials for Light Water Reactor Fuels

Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an accident tolerant fuel is and the benefits;

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Handbook of Generation IV Nuclear Reactors

Handbook of Generation IV Nuclear Reactors presents information on the current fleet of Nuclear Power Plants (NPPs) with water-cooled;

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Severe Accidents in Nuclear Reactors

Severe Accidents in Nuclear Reactors: Corium Retention Technologies and Insights presents an authoritative and practical analysis;

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Nuclear Reactor Thermal-Hydraulics

-cooled reactors, and provides a direction for the future thermal-hydraulic developments for water-cooled, including small modular reactors or SMR;

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Fast Spectrum Reactors

, along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a;

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Fast Spectrum Reactors

, along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a;

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Light Water Reactor Fuel Enrichment beyond the Five Per Cent Limit

platform to facilitate a comprehensive review of the current status, prospects and challenges associated with the use of fuels having enrichments;

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The fourth generation of nuclear reactors

International Forum with regard to safety, sustainability and economic efficiency. The book therefore describes, among other things, innovative water;

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Materials and Water Chemistry for Supercritical Water-cooled Reactors

Materials and Water Chemistry for Supercritical Water-cooled Reactors is unique in that it brings together materials and water;

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Dynamics and Control of Nuclear Reactors

studies and examples to demonstrate learning through problem solving, including an analysis of accidents at Three Mile Island, Chernobyl and;

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Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

of liquid metal cooled fast reactors worldwideDescribes the challenges in thermal hydraulics related to the design and safety analysis;

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Nuclear Power Plants

in primary circuits of pressurized water reactors and the fundamental stability analysis of hypothetical boiling and pressurized water reactors.;

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Sodium Fast Reactors with Closed Fuel Cycle

, analysis, and validation Sodium Fast Reactors with Closed Fuel Cycle is a valuable reference for industry professionals involved in the;

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Sodium Fast Reactors with Closed Fuel Cycle

, analysis, and validation Sodium Fast Reactors with Closed Fuel Cycle is a valuable reference for industry professionals involved in the;

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Heat Transfer and Hydrodynamics in Gas-Cooled Fuel Rod Assemblies

. Extensive experimental data made it possible to develop a number of universal calculating procedures and programmes for the analytical cell-by-cell;

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The Risks of Nuclear Energy Technology

of operating German Pressurized Water Reactors and Boiling Water Reactors including accident management measures introduced after the reactor accidents;

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Research Reactors for Development of Materials and Fuels for Innovative Nuclear Energy Systems

Presents an overview of research reactor capabilities and capacities in the development of fuels and materials for innovative nuclear;

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