Effects of thermal aging and neutron irradiation on the mechanical properties of stainless steel weld overlay cladding
Stainless steel weld overlay cladding was fabricated using the three-wire, series-arc method. Three layers of cladding were applied to a pressure vessel plate to provide adequate thickness for fabrication of test specimens. Since irradiation of the stainless steel cladding to 5 {times} 10{sup 19} neutrons/cm{sup 2} (>1 MeV) was conducted at 288{degrees}C for 1605 h, tensile, Charpy V-notch (CVN), precracked Charpy V-notch (PCVN), and compact fracture toughness specimens were thermally aged at 288{degrees}C for 1605 h. Additional specimens are being aged to 20,000 and 50,000 h. Thermal aging of three-wire, series-arc stainless steel weld overlay cladding at 288{degrees}C for 1604 h resulted in appreciable decrease (16%) in the CVN upper-shelf energy, but the effect on the 41-J transition temperature shift was very small (3{degrees}C). The combined effect, following neutron irradiation at 288{degrees}C to a fluence of 5 {times} 10{sup 19} neutrons/cm{sup 2} (>MeV), was a 22% reduction in the CVN upper-shelf energy and a 29{degrees}C shift at the 41-J level. The effect of thermal aging on tensile properties was very small or negligible. However, the combined effect after neutron irradiation was an increase in the yield strength (6 to 34% at test temperatures from 288 to {minus}125{degrees}C) and no apparent change in ultimate strength and total elongation. Also, neutron irradiation reduced the initiation fracture toughness (J{sub Ic}) much more than did thermal aging. However, irradiation slightly decreased the tearing modulus, but no reduction was caused by thermal aging alone. The effects of long-term thermal exposure times (20,000 and 50,000 h) will be investigated when the specimen become available.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6087069
- Report Number(s):
- CONF-910808-7; ON: DE92004443
- Resource Relation:
- Conference: 5. international symposium on environmental degradation on materials in nuclear power systems - water reactors, Monterey, CA (United States), 25-29 Aug 1991
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
STAINLESS STEEL-308
AGING
PHYSICAL RADIATION EFFECTS
ELONGATION
FRACTURE PROPERTIES
NEUTRONS
PRESSURE VESSELS
TENSILE PROPERTIES
ULTIMATE STRENGTH
WELDED JOINTS
ALLOYS
AUSTENITIC STEELS
BARYONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION RESISTANT ALLOYS
ELEMENTARY PARTICLES
FERMIONS
HADRONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MECHANICAL PROPERTIES
NICKEL ALLOYS
NUCLEONS
RADIATION EFFECTS
STAINLESS STEELS
STEEL-CR20NI11
STEELS
220200* - Nuclear Reactor Technology- Components & Accessories
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties