Experimental and Numerical Stability Investigations on Natural Circulation Boiling Water Reactors

Experimental and Numerical Stability Investigations on Natural Circulation Boiling Water Reactors PDF Author: Christian Pablo Marcel
Publisher: IOS Press
ISBN: 1586038036
Category : Technology & Engineering
Languages : en
Pages : 160

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Book Description
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.

Experimental and Numerical Stability Investigations on Natural Circulation Boiling Water Reactors

Experimental and Numerical Stability Investigations on Natural Circulation Boiling Water Reactors PDF Author: Christian Pablo Marcel
Publisher: IOS Press
ISBN: 1586038036
Category : Technology & Engineering
Languages : en
Pages : 160

Get Book Here

Book Description
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.

Handbook of Generation IV Nuclear Reactors

Handbook of Generation IV Nuclear Reactors PDF Author: Igor Pioro
Publisher: Woodhead Publishing
ISBN: 0128226536
Category : Technology & Engineering
Languages : en
Pages : 1112

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Book Description
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

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

Single-phase, Two-phase and Supercritical Natural Circulation Systems PDF Author: Pallippattu Krishnan Vijayan
Publisher: Woodhead Publishing
ISBN: 0081024878
Category : Technology & Engineering
Languages : en
Pages : 651

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Book Description
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

Natural Circulation in Water Cooled Nuclear Power Plants

Natural Circulation in Water Cooled Nuclear Power Plants PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 656

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Book Description
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.

Super Light Water Reactors and Super Fast Reactors

Super Light Water Reactors and Super Fast Reactors PDF Author: Yoshiaki Oka
Publisher: Springer Science & Business Media
ISBN: 1441960341
Category : Technology & Engineering
Languages : en
Pages : 664

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Book Description
Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1462

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Book Description
NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 484

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Book Description


TID.

TID. PDF Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 446

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Book Description


Heat Transfer and Fluid Flow

Heat Transfer and Fluid Flow PDF Author: James M. Jacobs
Publisher:
ISBN:
Category : Fluid dynamics
Languages : en
Pages : 444

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Book Description
A total of 2519 annotated references to the unclassified report literature is presented. Subjects covered under heat transfer and fluid flow include radioinduced heating; boiling; boiler, evaporators, pump, and heat exchanger design; hydrodynamics; coolants and their properties; thermal and flow instrumentation; high temperature materials; thermal properties of materials; and thermal insulation. Subjects covered less completely include thermodynamics; aerodynamics; high temperature corrosion; corrosion specific to heat transfer systems; erosion; mass transfer; corrosion film formation and effects; coolant processing and radioactivity; radiation effects of heat transfer materials; and pertinent data of thermonuclear processes. Subject, report number availability, and author indexes are given.

Indexed Bibliography of Current Nuclear Safety Literature

Indexed Bibliography of Current Nuclear Safety Literature PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 208

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Book Description