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Corrosion of zircaloy fuel cladding under irradiation. [CANDU]

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6615040
None
Research Organization:
Atomic Energy of Canada Ltd., Chalk River, Ontario
OSTI ID:
6615040
Report Number(s):
CONF-800607-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 34
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
CANDU TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CORROSION
FUEL CANS
HEAVY WATER MODERATED REACTORS
IRON ADDITIONS
IRON ALLOYS
MATERIALS
PRESSURE TUBE REACTORS
REACTOR MATERIALS
REACTORS
STRESSES
THERMAL REACTORS
THERMAL STRESSES
TIN ALLOYS
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS