Slow strain rate tensile tests in high temperature water of spectrally tailored irradiated type 316 materials for fusion reactor applications
Conference
·
OSTI ID:10140242
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
- Oak Ridge National Lab., TN (United States)
The susceptibility of neutron irradiated type 316 stainless to stress corrosion cracking in oxygenated pure water was investigated by Slow Strain Rate Technique (SSRT). The specimens had been irradiated to 8 dpa in the Oak Ridge Research Reactor (ORR) under fusion spectrally tailored condition to simulate radiation environment expected in the near-term water-cooled fusion reactor at temperatures of 60, 200, 330 and 400{degrees}C. SSRT tests were conducted at the same temperatures with irradiation for specimens irradiated at 60 and 200{degrees}C and at 300{degrees}C for specimens irradiated at 330 and 400{degrees}C. Intergranular cracks was observed on the specimens irradiated at higher two temperatures, while the specimens irradiated at lower two techniques showed completely ductile fracture. Crack initiation by transgranular type fracture was observed. On fractured grain facets apparent slip steps formed. Results of the SSRT were compared with those from specimens irradiated under LWR conditions and discussed.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10140242
- Report Number(s):
- CONF-920458--7; ON: DE92011783
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
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70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480
COMPONENT DEVELOPMENT
CORROSION AND EROSION
DAMAGING NEUTRON FLUENCE
MATERIALS STUDIES
MECHANICAL PROPERTIES
MECHANICAL TESTS
PHYSICAL RADIATION EFFECTS
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360103
360105
360106
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480
COMPONENT DEVELOPMENT
CORROSION AND EROSION
DAMAGING NEUTRON FLUENCE
MATERIALS STUDIES
MECHANICAL PROPERTIES
MECHANICAL TESTS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEEL-316
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STRESS CORROSION
TENSILE PROPERTIES
THERMONUCLEAR REACTOR MATERIALS