Development of a miniature-disk bending fatigue specimen
Creators
- 1. Oak Ridge National Lab., TN (United States)
- 2. Auburn Univ., AL (United States). Materials Engineering Program
Description
A miniature-disk bending fatigue specimen was earlier developed for testing materials to be used for fusion reactor applications. The specimen is based on a 3-mm-diameter transmission electron microscope disk. A second larger rectangular specimen was also developed, with dimensions of 30.16 by 4.76 by 0.76 mm. The specimens, made from annealed type 316 stainless steel, were testing using a specialized bending fatigue machine at temperatures of 25, 550, and 650 C. In the current study, the results are compared against standard full-size specimen results. Strain ranges were calculated using an analytical technique based on specimen geometry and material properties. For the rectangular specimen, strains were also measured using strain gauges attached to the gauge region. The calculated strains were then modified using a calibration factor based on the measurement. The rectangular specimen results were in good agreement with ASTM full-size specimen results. The miniature-disk specimen data fell below the other results, indicating that the analytical technique underestimates strain values. No clear temperature dependence was evident for the miniature-disk specimen, unlike larger specimens which show a degradation of fatigue properties with increasing temperature. The miniature-disk specimen results also show a greater scatter about the best-fit curve, which was attributed to greater sensitivity to misalignment
Additional details
Publishing Information
- Publisher
- American Society for Testing and Materials.
- Imprint Place
- Philadelphia, PA (United States)
- ISBN
- 0-8031-1869-4
- Imprint Title
- Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension
- Imprint Pagination
- 468 p.
- Journal Page Range
- p. 267-274.
Conference
- Title
- American Society for Testing and Materials (ASTM) international symposium on small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension.
- Dates
- 29-31 Jan 1992.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26000396
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; MECHANICAL TESTS; MINIATURIZATION; PHYSICAL RADIATION EFFECTS; SAMPLE PREPARATION; STAINLESS STEEL-316; THERMAL FATIGUE; THERMONUCLEAR REACTOR MATERIALS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; DATA; FATIGUE; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NUMERICAL DATA; RADIATION EFFECTS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; TESTING
Optional Information
- Secondary number(s)
- CONF-920146--.