Irradiation effects on strength and toughness of three-wire series- arc stainless steel weld overlay cladding
The potential for stainless steel cladding to improve the fracture behavior of an operating nuclear reactor pressure vessel, particularly during certain overcooling transients, may depend greatly on the properties of the irradiated cladding. Therefore, three-wire stainless steel cladding irradiated at temperatures and to fluences relevant to power reactor operation was examined. Postirradiation tensile testing results show that, in the test temperature range from {minus}125 to 288{degree}C, the yield strength increased by 8 to 30%, ductility increased insignificantly, with almost no change in ultimate tensile strength. All cladding exhibited ductile-to-brittle transition behavior during Charpy impact testing, because of the dominance of delta ferrite failures at low temperatures. On the upper shelf, energy was reduced 15 and 20%, while the lateral expansion was reduced 43 and 41%, owing to irradiation exposure of 2 and 5{times}10{sup 19} neutrons/cm{sup 2} (>1 MeV), respectively. In addition, radiation damage resulted in 13 and 28{degree}C shifts of the Charpy impact transition temperature at the 41-J level for the low and high fluences, respectively. Furthermore, irradiation exposure of 12.5-mm-thick compact specimens (0.5TCS), to an average fluence of 2.41 {times} 10{sup 19} neutrons/cm{sup 2} (>1 MeV), resulted in decreases in the initiation fracture toughness, J{sub Ic}, and the tearing modulus in the test temperature range. This is in agreement with the reduction in both the Charpy V-notch upper-shelf energy and the lateral expansion. 14 refs., 26 figs., 13 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USNRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7172259
- Report Number(s):
- NUREG/CR-5511; ORNL/TM-11439; ON: TI90008264; TRN: 90-008858
- Country of Publication:
- United States
- Language:
- English
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Effects of thermal aging and neutron irradiation on the mechanical properties of stainless steel weld overlay cladding
Effects of thermal aging and neutron irradiation on the mechanical properties of stainless steel weld overlay cladding
Related Subjects
36 MATERIALS SCIENCE
NUCLEAR POWER PLANTS
PRESSURE VESSELS
CLADDING
RADIATION EFFECTS
STAINLESS STEELS
WELDED JOINTS
AGING
CHARPY TEST
COMPILED DATA
DUCTILE-BRITTLE TRANSITIONS
FAILURE MODE ANALYSIS
FRACTURE PROPERTIES
IRRADIATION
MECHANICAL PROPERTIES
NEUTRON FLUENCE
POST-IRRADIATION EXAMINATION
REACTOR SAFETY
TEMPERATURE EFFECTS
YIELD STRENGTH
ALLOYS
CONTAINERS
DATA
DEPOSITION
DESTRUCTIVE TESTING
HIGH ALLOY STEELS
IMPACT TESTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS TESTING
MECHANICAL TESTS
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
SAFETY
STEELS
SURFACE COATING
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL POWER PLANTS
220200* - Nuclear Reactor Technology- Components & Accessories
220900 - Nuclear Reactor Technology- Reactor Safety
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties