Author: D. B. Stickler
Publisher:
ISBN:
Category :
Languages : en
Pages : 157
Book Description
Experimental study of liquid containment and heat transfer rates in a gas driven confined vortex is performed with reference to desired operating conditions for a liquid core nuclear rocket. Simple methods of containment and transport processes are used to scale the data to a predicted performance capability of a nominal 20,000 pound thrust, 1200 second specific impulse system. Molten fuel containment, as a two phase zone on the cylindrical cavity side walls, appears feasible at or above levels required for thermal neutron reactor criticality. Two potential problems are that the input gas flow distribution must be chosen to avoid freezing of the nuclear fuel at the cavity walls, and that the overshoot of the fuel temperature relative to the peak gas stagnation temperature may cause excessive fuel vapor loss. (Modified author abstract).
Heat Transfer and Containment Process in Two Phase Cavity Nuclear Reactor
Heat Transfer and Containment Processes in Two Phase Cavity Nuclear Reactor
Author: David Bruce Stickler
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 138
Book Description
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 138
Book Description
Nuclear Science Abstracts
Post-Dryout Heat Transfer
Author: G.F. Hewitt
Publisher: Routledge
ISBN: 1351423312
Category : Science
Languages : en
Pages : 446
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.
Publisher: Routledge
ISBN: 1351423312
Category : Science
Languages : en
Pages : 446
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.
Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems
Author: Jean J. Ginoux
Publisher: Hemisphere Pub
ISBN:
Category : Science
Languages : en
Pages : 488
Book Description
Publisher: Hemisphere Pub
ISBN:
Category : Science
Languages : en
Pages : 488
Book Description
Scientific and Technical Aerospace Reports
Two-phase Transport & Reactor Safety
Author: T. Nejat Veziroğlu
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 456
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 456
Book Description
Two-Phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems
Government Reports Announcements & Index
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1032
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.
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1032
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.