Iodine induced cracking of Zircaloy fuel cladding: a review
Conference
·
OSTI ID:4104474
- ed.
The evidence available on the factors affecting the stress corrosion cracking (SCC) of the Zircaloys in iodine at elevated temperatures is summarized. Cold work and irradiation hardening increase the susceptibility to SCC but other factors such as surface oxide conditions, crystallographic texture and residual stresses can also have appreciable effects. Evidence from fuel element testing together with the results of laboratory tests are now sufficient to permit the definite conclusion that fuel failures that occur after the sudden uprating of fuel elements can be caused by stress corrosion cracking. 48 references. (auth)
- Research Organization:
- Chalk River Nuclear Labs., Ontario
- NSA Number:
- NSA-33-013966
- OSTI ID:
- 4104474
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*FUEL CANS-- STRESS CORROSION
*PHWR TYPE REACTORS-- FUEL CANS
*ZIRCALOY-- STRESS CORROSION
210400* --Nuclear Power Plants--Power Reactors
Non- Breeding
Otherwise Moderated or Unmoderated
CRACKS
FUEL ELEMENTS
IODINE
N50210 --Metals
Ceramics
& Other Materials--Metals & Alloys--Corrosion & Erosion & Surface Phenomena
N77400* --Reactors--Power Reactors
Non-breeding
Otherwise Moderated or Unmoderated
POWER DISTRIBUTION
TENSILE PROPERTIES
URANIUM DIOXIDE
*PHWR TYPE REACTORS-- FUEL CANS
*ZIRCALOY-- STRESS CORROSION
210400* --Nuclear Power Plants--Power Reactors
Non- Breeding
Otherwise Moderated or Unmoderated
CRACKS
FUEL ELEMENTS
IODINE
N50210 --Metals
Ceramics
& Other Materials--Metals & Alloys--Corrosion & Erosion & Surface Phenomena
N77400* --Reactors--Power Reactors
Non-breeding
Otherwise Moderated or Unmoderated
POWER DISTRIBUTION
TENSILE PROPERTIES
URANIUM DIOXIDE