Search Results: bwr-refill-reflood-program-task-4-4-ccfl-refill-system-effects-tests-30-sector-experimental-task-plan

BWR refill-reflood program task 4.4, CCFL/refill system effects tests (30 ̊sector) experimental task plan

addendum B, SSTF CCFL/refill separate effect test plan

Author: D. G. Schumacher,U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation,Electric Power Research Institute,General Electric Company. Nuclear Engineering Division

Publisher: N.A


Category: Technology & Engineering

Page: N.A

View: 6824

BWR Refill-reflood Program Task 4.4, CCEL/refill System Effects Tests (30 ̊sector) Experimental Task Plan

Author: D. G. Schumacher

Publisher: N.A


Category: Boiling water reactors

Page: N.A

View: 9608

Monthly Catalog of United States Government Publications

Author: United States. Superintendent of Documents

Publisher: N.A


Category: Government publications

Page: N.A

View: 9213

February issue includes Appendix entitled Directory of United States Government periodicals and subscription publications; September issue includes List of depository libraries; June and December issues include semiannual index

Government Reports Annual Index

Author: N.A

Publisher: N.A


Category: Government reports announcements & index

Page: N.A

View: 2990

Government Reports Annual Index: Keyword A-L

Author: N.A

Publisher: N.A


Category: Government reports announcements & index

Page: N.A

View: 7171

Guidebook to Light Water Reactor Safety Analysis

Author: P. B. Abramson

Publisher: CRC Press

ISBN: 9780891162629

Category: Technology & Engineering

Page: 393

View: 8885

The Guidebook to Light Water Reactor Safety Analysis brings together government and expert researchers entrusted with maintaining the safety of reactors, preventing incidents, and for creating the guidelines for responding appropriately to emergency situations. It includes an overview presented by the U.S. Nuclear Regulatory Commission. One of the most relevant compendiums of its time, it's a volume of both historical and scientific significance and well worth the consideration of those currently involved with maintaining reactor safety..

Multi-phase Transport

Fundamentals, Reactor Safety, Applications

Author: T. Nejat Veziroğlu

Publisher: N.A

ISBN: 9780891162056

Category: Heat

Page: 2932

View: 5667

Nuclear Safety in Light Water Reactors

Severe Accident Phenomenology

Author: Bal Raj Sehgal

Publisher: Academic Press

ISBN: 0123884462

Category: Science

Page: 714

View: 1843

This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of nuclear power. This book emphasizes the prevention and management of severe accidents, in order to teach nuclear professionals how to mitigate potential risks to the public to the maximum extent possible. Engineers, researchers, students and the personnel of vendors, safety authorities and nuclear power generation organizations require the knowledge offered by this volume's globally renowned experts to ensure they obtain a core competency in nuclear safety. Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information Explains how developments in the field of LWR severe accidents have provided more accurate determinations of risk, thereby shedding new light on the debates surrounding nuclear power safety, particularly in light of the recent tragedy in Japan Concentrates on prevention and management of accidents, developing methodologies to estimate the consequences and associated risks

The thermal-hydraulics of a boiling water nuclear reactor

Author: Richard T. Lahey,Frederick J. Moody

Publisher: Amer Nuclear Society

ISBN: 9780894480379

Category: Science

Page: 631

View: 3217

This edition of the classic monograph gives a comprehensive overview of the thermal-hydraulic technology underlying the design, operation, and safety assessment of boiling water reactors. In addition, new material on pressure suppression containment technology is presented.

Thermal-Hydraulics of Water Cooled Nuclear Reactors

Author: Francesco D'Auria

Publisher: Woodhead Publishing

ISBN: 0081006799

Category: Technology & Engineering

Page: 1198

View: 910

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

Handbook of multiphase systems

Author: Gad Hetsroni

Publisher: Misc-Sci/Eng


Category: Science

Page: 1506

View: 3590

Good,No Highlights,No Markup,all pages are intact, Slight Shelfwear,may have the corners slightly dented, may have slight color changes/slightly damaged spine.

Numerical Simulation of Reactive Flow

Author: Elaine S. Oran,Jay P. Boris

Publisher: Cambridge University Press

ISBN: 9780521022361

Category: Science

Page: 552

View: 7793

Reactive flows encompass a broad range of physical phenomena, interacting over many different time and space scales. Such flows occur in combustion, chemical lasers, the earth's oceans and atmosphere, and stars and interstellar space. Despite the obvious physical differences in these flows, there is a striking similarity in the forms of their descriptive equations. Thus, the considerations and procedures for constructing numerical models of these systems are also similar, and these similarities can be exploited. Moreover, using the latest technology, what were once difficult and expensive computations can now be done on desktop computers. This book takes account of the explosive growth in computer technology and the greatly increased capacity for solving complex reactive flow problems that have occurred since the first edition of Numerical Simulation of Reactive Flow was published in 1987. It presents algorithms useful for reactive flow simulations, describes trade-offs involved in their use, and gives guidance for building and using models of complex reactive flows.

Natural circulation in water cooled nuclear power plants

phenomena models and methodology for system reliability assessments

Author: International Atomic Energy Agency

Publisher: Intl Atomic Energy Agency


Category: Business & Economics

Page: 635

View: 9314

This publication describes the present state of knowledge on natural circulation in water cooled nuclear power plants and passive system reliability, including 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.

Reactor Safeguards

International Series of Monographs on Nuclear Energy

Author: Charles R. Russell

Publisher: Elsevier

ISBN: 1483138860

Category: Science

Page: 400

View: 7270

Reactor Safeguards focuses on the measures and approaches in the safeguard of reactors. The book first discusses the development of nuclear reactors, including the emergence of radiation hazards, construction of nuclear reactors in Chicago, and containment of reactors. The text also focuses on radioactive materials; reactor kinetics; and control and safety systems of reactors. The text discusses the containment of nuclear reactors. Topics include nuclear excursions; combustion of reactor materials; melting of reactor fuels; design of containment structures; and size of breaks or leaks in cooling systems. The text also describes the dispersion of radioactive materials, including problems in operations, diffusion theory, and nomograms for graphical solutions. The book also highlights the possible damages that a nuclear reactor accident can produce. Considerations include the permissible dose of radiation, exposure to nuclear radiations, and evacuation from a contaminated area. The text is a valuable source of data for readers, engineers, and physicists who are responsible in hazard analysis and site selection.

Nuclear Thermal Hydraulics

Author: Hajime Akimoto,Yoshinari Anoda,Kazuyuki Takase,Hiroyuki Yoshida,Hidesada Tamai

Publisher: Springer

ISBN: 4431556036

Category: Technology & Engineering

Page: 458

View: 2565

This volume provides fundamentals of nuclear thermal–hydraulics for reactor design and safety assessment. It also describes the basis for assessing cooling performance of nuclear reactors under accidental conditions. The descriptions in this book are virtually self-contained, beyond the assumption that readers are familiar with the introductory levels of nuclear engineering. This book helps readers understand the processes for nuclear reactor plant design and the most important factors in nuclear thermal-hydraulics.

Thermal-Hydraulic Analysis of Nuclear Reactors

Author: Bahman Zohuri

Publisher: Springer

ISBN: 3319538292

Category: Technology & Engineering

Page: 835

View: 2888

This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.


a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods

Author: Gary A. Berna,EG&G Idaho,Pacific Northwest Laboratory,U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research

Publisher: N.A


Category: Nuclear fuel claddings

Page: 282

View: 4954

Decommissioning of nuclear facilities

an analysis of the variability of decommissioning cost estimates

Author: OECD Nuclear Energy Agency

Publisher: N.A


Category: Technology & Engineering

Page: 129

View: 3974

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