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Stress corrosion cracking of irradiated Zircaloy cladding under constant load conditions

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5149130
;
None
Research Organization:
GE, Pleasanton, Pleasanton, CA 94566
OSTI ID:
5149130
Report Number(s):
CONF-811103-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 39
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CLADDING
CORROSION
DEPOSITION
FUEL CANS
FUEL-CLADDING INTERACTIONS
IRON ADDITIONS
IRON ALLOYS
MATERIALS
PERFORMANCE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STATIC LOADS
STRESS CORROSION
SURFACE COATING
TIN ALLOYS
WATER COOLED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS