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1.

図書

図書
J.G.Collier, G.F.Hewitt原著 ; 中西重康 [ほか] 共訳
出版情報: 東京 : コロナ社, 1992.11  312p ; 22cm
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2.

図書

図書
John G. Collier
出版情報: New York ; London : McGraw-Hill International Book Co., c1981  xxxii, 435 p. ; 26 cm
シリーズ名: Advanced book program
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目次情報: 続きを見る
Introduction / 1:
The Basic Models / 2:
Empirical Treatments of Two-Phase Flow / 3:
Introduction to Convective Boiling / 4:
Subcooled Boiling Heat Transfer / 5:
Void Fraction and Pressure Drop in Subcooled Boiling / 6:
Saturated Boiling Heat Transfer / 7:
Critical Heat Flux in Forced Convective Flow / 8:
Vertical Uniformly Heated Tubes
More Complex Situations / 9:
Condensation / 10:
Conditions Influencing the Performance of Boiling and Condensing Systems / 11:
Multi-Component Boiling and Condensation / 12:
Appendix
Index
Introduction / 1:
The Basic Models / 2:
Empirical Treatments of Two-Phase Flow / 3:
3.

図書

図書
John G. Collier, Geoffrey F. Hewitt
出版情報: Washington, DC : Taylor & Francis, c2000  xv, 304 p. ; 24 cm
シリーズ名: Series in chemical and mechanical engineering
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目次情報: 続きを見る
Preface to Second Edition
Preface to First Edition
The Earth and Nuclear Power: Sources and Resources / 1:
Introduction / 1.1:
Forms of Energy / 1.1.1:
Units of Energy / 1.1.2:
Energy Conversion Process / 1.1.3:
Earth's Internal Heat Generation / 1.2:
The Earth's Energy Flow / 1.3:
The Fission Process / 1.4:
Thermal Energy Resources / 1.5:
References
Examples and Problems
Bibliography
How Reactors Work / 2:
Basic Components of a Nuclear Reactor / 2.1:
Thermal Reactors / 2.4:
Natural Uranium Graphite-Moderated (Magnox) Reactors / 2.4.1:
Advanced Gas-Cooled Reactors / 2.4.2:
Pressurized-Water Reactors / 2.4.3:
Boiling-Water Reactors / 2.4.4:
Natural Uranium Heavy Water-Moderated and-Cooled Reactors / 2.4.5:
Boiling-Water, Graphite-Moderated Direct-Cycle Reactor (RBMK) / 2.4.6:
Fast Reactors / 2.5:
Liquid Metal-Cooled Fast Breeder Reactors / 2.5.1:
Cooling Reactors / 3:
General Features of a Reactor Coolant / 3.1:
Principles of Heat Transfer / 3.3:
Gaseous Coolants / 3.4:
Air / 3.4.1:
Carbon Dioxide / 3.4.2:
Helium / 3.4.3:
Steam / 3.4.4:
Liquid Coolants / 3.5:
Light Water / 3.5.1:
Heavy Water / 3.5.2:
Organic Fluids / 3.5.3:
Molten Salts / 3.5.4:
Liquid Metals / 3.5.5:
Boiling Coolants / 3.6:
Water / 3.6.1:
Alternative Forms of Reactor Coolant Circuits / 3.6.2:
Loop-Type Circuits / 3.7.1:
Integral-Type Circuits / 3.7.2:
Pool-Type Circuits / 3.7.3:
Future Developments / 3.7.4:
Loss of Cooling / 4:
The Electric Kettle / 4.1:
Pressurized-Water Reactor / 4.3:
Operating States of the PWR / 4.3.1:
Energy Balances in the PWR under Fault Conditions / 4.3.2:
The Large-Break LOCA in the PWR / 4.3.3:
The Small-Break LOCA / 4.3.4:
Alternative ECCSs / 4.3.5:
Boiling-Water Reactor / 4.4:
Large-Break LOCA in a BWR (the Design Basis Accident) / 4.4.1:
Small-Break LOCAs in BWRs / 4.4.2:
CANDU Reactor / 4.5:
Gas-Cooled Reactors / 4.6:
Design Basis Accident for the AGR: Depressurization Fault / 4.6.1:
Sodium-Cooled Fast Reactor / 4.7:
Reference
Loss-of-Cooling Accidents: Some Examples / 5:
Incidents in Light Water-Cooled Reactors / 5.1:
The SL-1 Accident / 5.2.1:
The Millstone 1 Accident / 5.2.2:
The Browns Ferry Fire / 5.2.3:
The Three Mile Island (TMI) Accident / 5.2.4:
The Ginna Incident / 5.2.5:
Mihama 2 Incident / 5.2.6:
The Serious Accident at Chernobyl / 5.2.7:
Heavy Water--Moderated Reactors / 5.3:
The NXR Incident / 5.3.1:
The Core-Damage Incident at Lucens / 5.3.2:
The Windscale Fire / 5.4:
The Fuel Meltdown at St. Laurent / 5.4.2:
Seawater Ingress in the Hunterston BAGR Station / 5.4.3:
Fuel Damage during Charging at the Hinkley Point BAGR / 5.4.4:
Liquid Metal--Cooled Fast Reactors / 5.5:
The EBR-1 Meltdown Accident / 5.5.1:
Fuel Melting Incident at the Enrico Fermi 1 Fast Breeder Reactor / 5.5.2:
The International Nuclear Event Scale (INES) / 5.6:
Postulated Severe Accidents / 6:
Postulated Severe Accidents in Water-Cooled Reactors / 6.1:
Core Damage / 6.2.1:
Challenges to the Reactor Pressure Vessel / 6.2.2:
Challenges to the Reactor Containment / 6.2.3:
Mitigating the Consequences of Severe Accidents / 6.2.4:
Specific Phenomena relating to Severe Accidents / 6.3:
Fuel-Coolant Interactions:-"Steam Explosions" / 6.3.1:
Debris Beds and Their Cooling / 6.3.2:
Hydrogen Formation: Burning and Explosions / 6.3.3:
Containment Basement Melt-Through and Failure / 6.3.4:
Severe Accidents in Other Reactor Types / 6.4:
Fission Product Dispersion following Containment Failure / 6.5:
Cooling during Fuel Removal and Processing / 7:
Refueling / 7.1:
Refueling of Gas-Cooled Reactors / 7.2.1:
Refueling of CANDU Reactors / 7.2.2:
Refueling of Light-Water Reactors / 7.2.3:
Refueling of Liquid Metal-Cooled Fast Breeder Reactors / 7.2.4:
Spent Fuel Storage and Transport / 7.3:
Reprocessing Plant / 7.4:
Cooling and Disposing of the Waste / 8:
Classification of Waste Products / 8.1:
Fission Products and Their Biological Significance / 8.3:
Options for Nuclear Waste Disposal / 8.4:
Long-Term Storage and Disposal of Spent Nuclear Fuel / 8.5:
Ultimate Disposal in Salt Deposits / 8.5.1:
Geological Storage / 8.5.2:
Storage and Disposal of Fission Products from Reprocessing Plants / 8.6:
Disposal of Other Materials / 8.7:
Fusion Energy: Prospect for the Future / 9:
The Fusion Process / 9.1:
Confinement / 9.3:
Current Technical Position / 9.4:
Conclusions / 9.5:
Index
Preface to Second Edition
Preface to First Edition
The Earth and Nuclear Power: Sources and Resources / 1:
4.

図書

図書
John G. Collier
出版情報: London ; New York : McGraw-Hill, c1972  xxxi, 421 p. ; 26 cm
所蔵情報: loading…
目次情報: 続きを見る
Introduction / 1:
The Basic Models / 2:
Empirical Treatments of Two-Phase Flow / 3:
Introduction to Convective Boiling / 4:
Subcooled Boiling Heat Transfer / 5:
Void Fraction and Pressure Drop in Subcooled Boiling / 6:
Saturated Boiling Heat Transfer / 7:
Critical Heat Flux in Forced Convective Flow / 8:
Vertical Uniformly Heated Tubes
More Complex Situations / 9:
Condensation / 10:
Conditions Influencing the Performance of Boiling and Condensing Systems / 11:
Multi-Component Boiling and Condensation / 12:
Appendix
Index
Introduction / 1:
The Basic Models / 2:
Empirical Treatments of Two-Phase Flow / 3:
5.

図書

図書
John G. Collier and John R. Thome
出版情報: Oxford : Clarendon Press , New York : Oxford University Press, 1994  xliii, 596 p. ; 25 cm
シリーズ名: The Oxford engineering science series ; 38
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目次情報: 続きを見る
Introduction / 1:
The Basic Models / 2:
Empirical Treatments of Two-Phase Flow / 3:
Introduction to Convective Boiling / 4:
Subcooled Boiling Heat Transfer / 5:
Void Fraction and Pressure Drop in Subcooled Boiling / 6:
Saturated Boiling Heat Transfer / 7:
Critical Heat Flux in Forced Convective Flow / 8:
Vertical Uniformly Heated Tubes
More Complex Situations / 9:
Condensation / 10:
Conditions Influencing the Performance of Boiling and Condensing Systems / 11:
Multi-Component Boiling and Condensation / 12:
Appendix
Index
Introduction / 1:
The Basic Models / 2:
Empirical Treatments of Two-Phase Flow / 3:
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