Author: Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 620
Book Description
Proceedings of the Topical Meeting on Thermal Reactor Safety
Author: Proceedings of the International ANS/ENS Topical Meeting on Thermal Reactor Safety, San Diego, California, U.S.A., February 2-6, 1986
Author: American Nuclear SocietyPublisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 434
Book Description
Proceedings of the National Topical Meeting on Fast Reactor Systems, Materials and Components
Author: J. F. WeissenbergPublisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 484
Book Description
Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting
Author: Reactor Safety Research Semiannual Report
Author: Nuclear Safety
Author: Thermal-Hydraulics of Water Cooled Nuclear Reactors
Author: Francesco D'AuriaPublisher: Woodhead Publishing
ISBN: 0081006799
Category : Technology & Engineering
Languages : en
Pages : 1200
Book Description
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
Fission Product Processes In Reactor Accidents
Author: J. T. RogersPublisher: CRC Press
ISBN: 1000107310
Category : Science
Languages : en
Pages : 883
Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.
Energy Research Abstracts
Author: Dynamic Simulation of Sodium Cooled Fast Reactors
Author: G VaidyanathanPublisher: CRC Press
ISBN: 1000779548
Category : Technology & Engineering
Languages : en
Pages : 273
Book Description
This book provides the basis of simulating a nuclear plant, in understanding the knowledge of how such simulations help in assuring the safety of the plants, thereby protecting the public from accidents. It provides the reader with an in-depth knowledge about modeling the thermal and flow processes in a fast reactor and gives an idea about the different numerical solution methods. The text highlights the application of the simulation to typical sodium-cooled fast reactor. The book • Discusses mathematical modeling of the heat transfer process in a fast reactor cooled by sodium. • Compares different numerical techniques and brings out the best one for the solution of the models. • Provides a methodology of validation based on experiments. • Examines modeling and simulation aspects necessary for the safe design of a fast reactor. • Emphasizes plant dynamics aspects, which is important for relating the interaction between the components in the heat transport systems. • Discusses the application of the models to the design of a sodium-cooled fast reactor It will serve as an ideal reference text for senior undergraduate, graduate students, and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.