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STP 1354
Zirconium in the Nuclear Industry: 12th International Symposium
960 стр.
Действует
Печатное издание
613.08 $ (включая НДС 20%)
Разработчик:
Зарубежные/ASTM
Тематика:
Other Nonferrous Metals
Описание
Краткое описание

44 papers discuss the history, processing, use, and propertiesof Zirconium and its alloys. Nearly half are concerned with thecorrosion and hydriding of different Zirconium alloys. Thetechniques used to characterize the oxides and theirmicrostructures and properties have become very advanced. Theindustry, including producers and users, expects that the work willlead to important conclusions about alloy development, optimizationof the processing parameters, and station operating procedures sothat the current and new Zirconium materials will continue tooperate reliably to very high neutron fluences.

Seven major topics include:

• Properties at High Neutron Fluences

• Hydrogen and Temperature Effects

• Deformation and Fracture Studies

• Processing and Alloy Development

• Effect of Composition and Microstructure on Corrosion

• Corrosion Simulation and the Effect of the Environment

• Effects of Oxides on Oxidation and H Pickup Rates

Audience:Scientists and engineers involved in the production andproperties of components for use in nuclear reactors, theirbehavior during service and the property changes that occur withincreasing neutron fluences.