Zirconium in the nuclear industry
Conference
·
OSTI ID:5501594
This book contains papers from the 9th International Symposium on Zirconium in the Nuclear Industry. Zirconium alloys, especially Zircaloy-2, Zircaloy-4, and Zr-2.5Nb, have been the main materials used in the core of nuclear power plants. Because of the recent trends in the nuclear industry towards higher fuel discharge burnups for better fuel utilization, and higher heat ratings and coolant temperatures for better thermal efficiency, interest in zirconium alloys has increased. It follows that corrosion-a topic of concern-has high coverage in this book. Other topics discussed are mechanical properties of zirconium alloys, and alloy fabrication.
- OSTI ID:
- 5501594
- Report Number(s):
- CONF-901107--; ISBN: 0-8031-1463X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105* -- Metals & Alloys-- Corrosion & Erosion
360106 -- Metals & Alloys-- Radiation Effects
ABSTRACTS
ALLOY-ZR98SN-2
ALLOY-ZR98SN-4
ALLOYS
CHEMICAL COMPOSITION
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CORROSION RESISTANCE
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
ENVIRONMENTAL EFFECTS
FABRICATION
FUEL-CLADDING INTERACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
IRON ADDITIONS
IRON ALLOYS
LEADING ABSTRACT
MATERIALS
MATERIALS TESTING
MATERIALS WORKING
MECHANICAL PROPERTIES
MEETINGS
MICROSTRUCTURE
NICKEL ADDITIONS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
PRESSURE TUBES
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RELIABILITY
TESTING
THERMAL REACTORS
THERMOMECHANICAL TREATMENTS
TIN ALLOYS
TUBES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YIELD STRENGTH
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105* -- Metals & Alloys-- Corrosion & Erosion
360106 -- Metals & Alloys-- Radiation Effects
ABSTRACTS
ALLOY-ZR98SN-2
ALLOY-ZR98SN-4
ALLOYS
CHEMICAL COMPOSITION
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CORROSION RESISTANCE
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
ENVIRONMENTAL EFFECTS
FABRICATION
FUEL-CLADDING INTERACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
IRON ADDITIONS
IRON ALLOYS
LEADING ABSTRACT
MATERIALS
MATERIALS TESTING
MATERIALS WORKING
MECHANICAL PROPERTIES
MEETINGS
MICROSTRUCTURE
NICKEL ADDITIONS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
PRESSURE TUBES
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RELIABILITY
TESTING
THERMAL REACTORS
THERMOMECHANICAL TREATMENTS
TIN ALLOYS
TUBES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YIELD STRENGTH
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS