Experimental and Numerical Stability Investigations on Natural Circulation Boiling Water Reactors
Experimental and Numerical Stability Investigations on Natural Circulation Boiling Water Reactors

Author: Christian Pablo Marcel

Publisher: IOS Press

Published: 2007

Total Pages: 160

ISBN-13: 1586038036

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In the design of novel nuclear reactors active systems are replaced by passive ones in order to reduce the risk of failure. For that reason natural circulation is being considered as the primary cooling mechanism in next generation nuclear reactor designs such as the natural circulation boiling water reactor (BWR). In such a reactor, however, the flow is not a controlled parameter but is dependent on the power. As a result, the dynamical behavior significantly differs from that in conventional forced circulation BWRs. For that reason, predicting the stability characteristics of these reactors has to be carefully studied. In this work, a number of open issues are investigated regarding the stability of natural circulation BWRs (e.g. margins to instabilities at rated conditions, interaction between the thermal-hydraulics and the neutronics, and the occurrence of flashing induced instabilities) with a strong emphasis on experimental evidence.

High Performance Light Water Reactor
High Performance Light Water Reactor

Author: Thomas Schulenberg

Publisher: KIT Scientific Publishing

Published: 2014-07-28

Total Pages: 258

ISBN-13: 3866448171

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Results of the project "High Performance Light Water Reactor--Phase 2," carried out September 2006-February 2010 as part of the 6th European Framework Program.

Handbook of Generation IV Nuclear Reactors
Handbook of Generation IV Nuclear Reactors

Author: Igor Pioro

Publisher: Woodhead Publishing

Published: 2022-12-07

Total Pages: 1112

ISBN-13: 0128226536

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Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. - Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors - Includes new trends and developments since the first publication, as well as brand new case studies and appendices - Covers the latest research, developments and design information surrounding generation IV nuclear reactors

An Experimental and Modelling Study of Natural-circulation Boiling Water Reactor Dynamics
An Experimental and Modelling Study of Natural-circulation Boiling Water Reactor Dynamics

Author: Róbert Zboray

Publisher: IOS Press

Published: 2002

Total Pages: 178

ISBN-13:

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Contents of this Doctoral Dissertation include: Understanding the linear stability characteristics of BWRs, Experiments on the stability of the Desire facility, Applications of the reducer-order model, Numerical analysis of the nonlinear dynamics of BWRs, Experiments on the nonlinear dynamics of natural-circulation two-phase flows, Experiments on the neutronic-thermalhydraulic stability, Conclusions and Discussion

Natural Circulation in Water Cooled Nuclear Power Plants
Natural Circulation in Water Cooled Nuclear Power Plants

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2005

Total Pages: 656

ISBN-13:

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Describes the state of knowledge of natural circulation in water cooled nuclear power plants and passive system reliability. The publication presents information on phenomena, models, predictive tools and experiments that currently support design and analysis of natural circulation systems, and highlights areas where additional research is needed.

Thermal-Hydraulics of Water Cooled Nuclear Reactors
Thermal-Hydraulics of Water Cooled Nuclear Reactors

Author: Francesco D'Auria

Publisher: Woodhead Publishing

Published: 2017-05-18

Total Pages: 1200

ISBN-13: 0081006799

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Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. - Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors - Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) - Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes - Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants

Single-phase, Two-phase and Supercritical Natural Circulation Systems
Single-phase, Two-phase and Supercritical Natural Circulation Systems

Author: Pallippattu Krishnan Vijayan

Publisher: Woodhead Publishing

Published: 2019-06-19

Total Pages: 651

ISBN-13: 0081024878

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Single-Phase, Two-Phase and Supercritical Natural Circulation Systems provides readers with a deep understanding of natural circulation systems. This book equips the reader with an understanding on how to detect unstable loops to ensure plant safety and reliability, calculate heat transport capabilities, and design effective natural circulation loops, stability maps and parallel channel systems. Each chapter begins with an introduction to the circulation system before discussing each element in detail and analyzing its effect on the performance of the system. The book also presents thermosyphon heat transport devices in nuclear and other industrial plants, a common information need for students and researchers alike. This book is invaluable for engineers, designers, operators and consultants in nuclear, mechanical, electrical and chemical disciplines. - Presents single-phase, two-phase and supercritical natural circulation systems together in one resource to fill an existing knowledge gap - Guides the reader through relevant processes, such as designing, analyzing and generating stability maps and natural circulation loops, calculating heat transport capabilities, and maintaining natural circulation system operations - Includes global case studies and examples to increase understanding, along with important IAEA standards and procedures

Scientific and Technical Aerospace Reports
Scientific and Technical Aerospace Reports

Author:

Publisher:

Published: 1968

Total Pages: 1252

ISBN-13:

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Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.