Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: Fundamental aspects of two-phase flow and boiling heat transfer PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: Fundamental aspects of two-phase flow and boiling heat transfer PDF full book. Access full book title Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: Fundamental aspects of two-phase flow and boiling heat transfer by . Download full books in PDF and EPUB format.
Author:
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 804
Get Book
Book Description
Author:
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 804
Get Book
Book Description
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1474
Get Book
Book Description
Author:
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 872
Get Book
Book Description
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 806
Get Book
Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 880
Get Book
Book Description
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 928
Get Book
Book Description
Author: Sadik KakaƧ
Publisher: Springer Science & Business Media
ISBN: 9400968450
Category : Science
Languages : en
Pages : 465
Get Book
Book Description
Over the past two decades, two-phase flow and heat transfer problems associated with two-phase phenomena have been a challenge to many investigators. Two-phase flow applications are found in a wide range of engineering systems, such as nuclear and conventional power plants, evaporators of refrigeration systems and a wide vari ety of evaporative and condensive heat exchangers in the chemical industry. This publication is based on the invited lectures presented at the NATO Advanced Research Workshop on the Advances in Two-Phase Flow and Heat Transfer. The Horkshop was attended by more than 50 leading scientists and practicing engineers who work actively on two-phase flow and heat transfer research and applications in dif ferent sectors (academia, government, industry) of member countries of NATO. Some scientific leaders and experts on the subject matter from the non-NATO countries were also invited. They convened to discuss the state-of-the-art in two-phase flow and heat transfer and formulated recommendations for future research directions. To achieve these goals, invited key papers and a limited number of contributions were presented and discussed. The specific aspects of the subject were treated in depth in the panel sessions, and the unresolved problems identified. Suitable as a practical reference, these volumes incorporate a systematic approach to two-phase flow analysis.
Author: G.F. Hewitt
Publisher: Routledge
ISBN: 1351423312
Category : Science
Languages : en
Pages : 257
Get Book
Book Description
The study of post-dryout heat transfer has generated great interest because of its importance in determining maximum clad temperature in nuclear reactor loss-of-coolant accidents (LOCAs). An associated phenomenon, the deterioration of heat transfer in boiling, is significant to other industrial sectors. This book provides comprehensive coverage of post-dryout heat transfer, discussing such essential topics as post-dryout heat transfer in dispersed flow, interpretation and use of transient data in surface rewetting by reinstatement of flow or by reducing heat flux, rod bundles, two-phase flow occurrences in the post-dryout region, various methods for predicting ""inverted annular flow,"" and new experiments for measuring thermodynamic nonequilibrium with probes in the channel. The book also presents a basis for independent safety assessment of nuclear reactors and chemical plant systems where post-dryout heat transfer may occur. Post-Dryout Heat Transfer will be a useful reference for researchers and professionals in the nuclear and chemical production industries.
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 984
Get Book
Book Description
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 414
Get Book
Book Description