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Title: Degradation of mechanical properties of stainless steel cladding due to neutron irradiation and thermal aging

Conference ·
OSTI ID:10183357

Thermal aging of three-wire series-arc stainless steel weld overlay cladding at 288{degrees}C for 1605 h resulted in an appreciable decrease (16%) in the Charpy V-notch (CVN) upper-shelf energy (USE), 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 X 10{sup 19} neutrons/cm{sup 2} (>1 MeV) was a 22% reduction in the USE and a 29{degrees}C shift in the 41-J transition temperature. The effect of thermal aging on tensile properties was very small. However, the combined effect of irradiation and aging was an increase in the yield strength (6 to 34% at test temperatures from 288 to -125{degrees}C) and no apparent change in ultimate tensile strength or total elongation. Neutron irradiation reduced the initiation fracture toughness (J{sub {kappa}}) much more than did thermal aging alone. 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 specimens become available. Also, long-term thermal exposure of the three-wire cladding as well as type 308 stainless steel weld materials at 343{degrees}C is in progress.

Research Organization:
Oak Ridge National Lab., TN (United States)
Sponsoring Organization:
Nuclear Regulatory Commission, Washington, DC (United States)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
10183357
Report Number(s):
CONF-920673-24; ON: TI94018945; TRN: 94:018989
Resource Relation:
Conference: 16. annual symposium of American Society of Testing and Materials (ASTM) on effects of radiation on materials,Denver, CO (United States),21-25 Jun 1992; Other Information: PBD: [1994]
Country of Publication:
United States
Language:
English