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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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Severe Accidents in Nuclear Reactors

of the latest severe accident management strategies based on previous events and experiments. Written for utilities and industries operating and;

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Developments in the Analysis and Management of Combustible Gases in Severe Accidents in Water Cooled Reactors following the Fukushima Daiichi Accident

Following the accident at the Fukushima Daiichi nuclear power plant, combustible gas behaviour and related accident management measures;

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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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Analysis of Options and Experimental Examination of Fuels for Water Cooled Reactors with Increased Accident Tolerance (ACTOF)

the development of modelling capacity to predict the behaviour of the components and the integral performance of accident tolerant fuel;

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

in plant operation for 97% of light and heavy water-cooled nuclear power units operated worldwide during the period 2006-2015. Data on fuel;

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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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Dynamics and Control of Nuclear Reactors

resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic;

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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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The fourth generation of nuclear reactors

- and liquid-metal-cooled reactors, high-temperature and molten-salt reactors, and discusses their significance for the economy and society;

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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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Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

of liquid metal cooled fast reactorsIncludes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor;

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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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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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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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Sodium Fast Reactors with Closed Fuel Cycle

coolant circuits, fuel handling, instrumentation and control, energy conversion, and containment systems Provides design codes and standards with;

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Sodium Fast Reactors with Closed Fuel Cycle

coolant circuits, fuel handling, instrumentation and control, energy conversion, and containment systems Provides design codes and standards with;

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Benchmark Analysis of EBR-II Shutdown Heat Removal Tests

safety codes used in the analyses of liquid metal thermal hydraulics and neutronics phenomena in sodium cooled fast reactors. The publication;

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Nuclear Power Plants

This book explores nuclear power plants which stand on the border between humanity's greatest hopes and its deepest fears for the future;

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Advances in Light Water Reactor Technologies

digital I&C systems and seismic design and evaluation described at length. This book is ideal for researchers and engineers working in nuclear;

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Stress Corrosion Cracking Nickel Alloys

alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France's leading center for nuclear research. This book assesses his work;

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Advances in Light Water Reactor Technologies

digital I&C systems and seismic design and evaluation described at length. This book is ideal for researchers and engineers working in nuclear;

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Steam Generators

Mihaela Duinea presents and elaborates upon a study for the application of steam generators in modelling and simulation of their operation;

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Natural circulation phenomena and modelling for advanced water cooled reactors

and natural circulation, and a methodology for examining passive system reliability.;

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