System-Level Heat Transfer Analysis, Thermal- Mechanical Cyclic Stress Analysis, and Environmental Fatigue Modeling of a Two-Loop Pressurized Water Reactor. A Preliminary Study
- Argonne National Lab. (ANL), Argonne, IL (United States)
This report provides an update on an assessment of environmentally assisted fatigue for light water reactor components under extended service conditions. This report is a deliverable in April 2015 under the work package for environmentally assisted fatigue under DOE's Light Water Reactor Sustainability program. In this report, updates are discussed related to a system level preliminary finite element model of a two-loop pressurized water reactor (PWR). Based on this model, system-level heat transfer analysis and subsequent thermal-mechanical stress analysis were performed for typical design-basis thermal-mechanical fatigue cycles. The in-air fatigue lives of components, such as the hot and cold legs, were estimated on the basis of stress analysis results, ASME in-air fatigue life estimation criteria, and fatigue design curves. Furthermore, environmental correction factors and associated PWR environment fatigue lives for the hot and cold legs were estimated by using estimated stress and strain histories and the approach described in NUREG-6909. The discussed models and results are very preliminary. Further advancement of the discussed model is required for more accurate life prediction of reactor components. This report only presents the work related to finite element modelling activities. However, in between multiple tensile and fatigue tests were conducted. The related experimental results will be presented in the year-end report.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy; USDOE Office of Nuclear Energy, Office of Nuclear Reactor Technologies, Light Water Reactor Sustainability Program
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1179020
- Report Number(s):
- ANL/LWRS-15/01; 115302
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
environmental fatigue modeling
finite element modeling
finite element modeling
thermal structural analysis
full scale reactor model
pressurized water reactor (PWR)
reactor coolant system
environmental fatigue modeling
full scale reactor model
pressurized water reactor (PWR)
reactor coolant system
thermal structural analysis