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          <dc:identifier>https://hdl.handle.net/2286/R.I.44086</dc:identifier>
                  <dc:rights>http://rightsstatements.org/vocab/InC/1.0/</dc:rights>
          <dc:rights>All Rights Reserved</dc:rights>
                  <dc:date>2017</dc:date>
                  <dc:format>111 pages</dc:format>
                  <dc:type>Doctoral Dissertation</dc:type>
          <dc:type>Academic theses</dc:type>
          <dc:type>Text</dc:type>
                  <dc:language>eng</dc:language>
                  <dc:contributor>Tahir, Fraaz</dc:contributor>
          <dc:contributor>Liu, Yongming</dc:contributor>
          <dc:contributor>Jiang, Hanqing</dc:contributor>
          <dc:contributor>Rajagopalan, Jagannathan</dc:contributor>
          <dc:contributor>Oswald, Jay</dc:contributor>
          <dc:contributor>Jiao, Yang</dc:contributor>
          <dc:contributor>Arizona State University</dc:contributor>
                  <dc:description>Doctoral Dissertation Mechanical Engineering 2017</dc:description>
          <dc:description>The Very High Temperature Reactor (VHTR) is one of six conceptual designs proposed for Generation IV nuclear reactors. Alloy 617, a solid solution strengthened Ni-base superalloy, is currently the primary candidate material for the tubing of the Intermediate Heat Exchanger (IHX) in the VHTR design. Steady-state operation of the nuclear power plant at elevated temperatures leads to creep deformation, whereas loading transients including startup and shutdown generate fatigue. A detailed understanding of the creep-fatigue interaction in Alloy 617 is necessary before it can be considered as a material for nuclear construction in ASME Boiler and Pressure Vessel Code. Current design codes for components undergoing creep-fatigue interaction at elevated temperatures require creep-fatigue testing data covering the entire range from fatigue-dominant to creep-dominant loading. Classical strain-controlled tests, which produce stress relaxation during the hold period, show a saturation in cycle life with increasing hold periods due to the rapid stress-relaxation of Alloy 617 at high temperatures. Therefore, applying longer hold time in these tests cannot generate creep-dominated failure. In this study, uniaxial isothermal creep-fatigue tests with non-traditional loading waveforms were designed and performed at 850 and 950°C, with an objective of generating test data in the creep-dominant regime. The new loading waveforms are hybrid strain-controlled and force-controlled testing which avoid stress relaxation during the creep hold. The experimental data showed varying proportions of creep and fatigue damage, and provided evidence for the inadequacy of the widely-used time fraction rule for estimating creep damage under creep-fatigue conditions. Micro-scale damage features in failed test specimens, such as fatigue cracks and creep voids, were quantified using a Scanning Electron Microscope (SEM) to find a correlation between creep and fatigue damage. Quantitative statistical imaging analysis showed that the microstructural damage features (cracks and voids) are correlated with a new mechanical driving force parameter. The results from this image-based damage analysis were used to develop a phenomenological life-prediction methodology called the effective time fraction approach. Finally, the constitutive creep-fatigue response of the material at 950°C was modeled using a unified viscoplastic model coupled with a damage accumulation model. The simulation results were used to validate an energy-based constitutive life-prediction model, as a mechanistic model for potential component and structure level creep-fatigue analysis.</dc:description>
                  <dc:subject>Mechanical Engineering</dc:subject>
          <dc:subject>Materials Science</dc:subject>
          <dc:subject>Engineering</dc:subject>
          <dc:subject>Creep</dc:subject>
          <dc:subject>Fatigue</dc:subject>
          <dc:subject>life prediction</dc:subject>
                  <dc:title>Creep-Fatigue Damage Investigation and Modeling of Alloy 617 at High Temperatures</dc:title></oai_dc:dc></metadata></record></GetRecord></OAI-PMH>
