RESIDUAL STRESS AND STRESS-CORROSION CRACKING OF TYPE-304 STAINLESS STEEL FUEL CLADDING.
Technical Report
·
OSTI ID:4491331
- Research Organization:
- General Electric Co., San Jose, Calif. Nuclear Fuels Dept.
- NSA Number:
- NSA-22-050730
- OSTI ID:
- 4491331
- Report Number(s):
- GEAP--4221
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ANALYSIS
BIG ROCK POINT
BIG ROCK POINT POWER REACTOR/fuel elements for
residual stress measurements in Type 304 stainless steel-clad uranium oxide (UO )
FUEL CANS
FUEL ELEMENTS
N38150* --Power Reactor Development--Fuels
NEUTRONS
NEUTRONS/effects on residual stress in Type 304 stainless steel-clad uranium oxide (UO$sub 2$) fuel elements
analysis of
POWER PLANTS
RADIATION EFFECTS
REACTORS
STAINLESS STEEL-304
STAINLESS STEEL/radiation effects on residual stress in Type 304
analysis of neutron
STAINLESS STEELS
STRESSES
URANIUM DIOXIDE
VALLECITOS BOILING-WATER REACTOR/fuel elements for
residual stress measurements for Type 304 stainless steel-clad uranium oxide (UO )
VBWR
BIG ROCK POINT
BIG ROCK POINT POWER REACTOR/fuel elements for
residual stress measurements in Type 304 stainless steel-clad uranium oxide (UO )
FUEL CANS
FUEL ELEMENTS
N38150* --Power Reactor Development--Fuels
NEUTRONS
NEUTRONS/effects on residual stress in Type 304 stainless steel-clad uranium oxide (UO$sub 2$) fuel elements
analysis of
POWER PLANTS
RADIATION EFFECTS
REACTORS
STAINLESS STEEL-304
STAINLESS STEEL/radiation effects on residual stress in Type 304
analysis of neutron
STAINLESS STEELS
STRESSES
URANIUM DIOXIDE
VALLECITOS BOILING-WATER REACTOR/fuel elements for
residual stress measurements for Type 304 stainless steel-clad uranium oxide (UO )
VBWR