CFD-grade Experiments Addressing Thermal Fatigue in Nuclear Reactor Branch Lines
- University of Michigan: 2355 Bonisteel Blvd, Ann Arbor, MI 48109 (United States)
Thermal fatigue has been identified as one of the main degradation mechanisms contributing to Loss of Coolant Accident frequencies in Light Water Reactors (LWRs). Thermal fatigue in stagnant branch lines departing from hot or cold legs of LWRs has become of high interest to the nuclear industry, as the current management program has had mixed effectiveness in preventing loss of power incidents. In fact, at least 8 such events involving branch lines have been registered at US plants over the past 2 years. Thermal cycling in a branch line occurs at the fluctuating boundary created by the penetration of hot fluid from the main flow into the cold stagnant fluid of the branch line. Penetration occurs as the fast moving flow of the main line crosses the opening of a branch line, causing cavity flow. Turbulent cavity flow dissipates to a disturbed flow further into the branch line and then to a laminar spiral flow. At the extent of the spiral flow, hot and cold fluids stratify to create the fluctuating boundary of interest. Qualitative experimental techniques, such as visualization of tracer particles, have been employed in past research efforts to capture the large scale evolution from cavity flow to the formation of the fluctuating stratified layer. The insight gained has been crucial in understanding the fundamentals of thermal cycling and stratification in branch lines; however, this qualitative information is insufficient for improving the current methods of predicting thermal fatigue in branch lines. High resolution quantitative measurements of the flow, capturing the small scale motions that affect the thermal cycling at the pipe wall, are needed to shed more light on the phenomenon and improve the industry fatigue management program, especially in terms of reliability. In the work presented here, time-resolved particle image velocimetry (PIV) is employed to investigate the flow in a stagnant branch line. Both time-averaged and time-dependent velocity fields of interest were captured, providing the groundwork for the experimental campaign that will be translated into model enhancement. (authors)
- OSTI ID:
- 23042948
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 115; Conference: 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, NV (United States), 6-10 Nov 2016; Other Information: Country of input: France; 3 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US); ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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