Design and Analysis of an Advanced Three-Point Bend Test Approach for Miniature Irradiated Disk Specimens
[1];
[2];
[3];
[4]
- Univ. of Illinois at Urbana-Champaign, IL (United States). Dept. of Nuclear, Plasma, and Radiological Engineering
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Fuel Cycle Division
- Pennsylvania State Univ., University Park, PA (United States). Dept. of Nuclear Engineering
Candidate tungsten armor materials in a magnetic confinement fusion device must be able to withstand thermal variation that leads to internal stresses caused by the impinging heat load. In addition, the thermomechanical properties of these materials are degraded by irradiation-induced defect accumulation. Fission reactor–based irradiation data are used to predict the fusion neutron damage and property change. This study examines the motivation and design of a custom-designed three-point bend test for neutron-irradiated disk specimens that are 3 mm in diameter to be able to define the flexural strength of advanced tungsten materials, alloys, and composites—and to the extent that embrittlement occurs after neutron irradiation. The theory provided shows a calculation for the flexural deflection and shear deflection due to the small-geometry constraints. A finite element deformation analysis is performed to evaluate the mechanical stress field of disk bend specimens. The stress values above 80% of the maximum stress are concentrated in 2.4 mm of the 3.0-mm length of the centerline across the tungsten disk diameter. A bend test fixture has been designed and fabricated to enable testing of these specimens with precisely engineered tolerance and minimal machine compliance. This fixture will be able to be placed inside a universal testing frame at elevated temperatures for the mechanical property evaluation of future neutron-irradiated disk specimens.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1819596
- Journal Information:
- Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 7-8 Vol. 77; ISSN 1536-1055
- Publisher:
- American Nuclear SocietyCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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