Experimental study on high cycle thermal fatigue in T-junction. Effect of local flow velocity on transfer of temperature fluctuation from fluid to structure
- 1. Japan Atomic Energy Agency, Oarai, Ibaraki (Japan)
Description
A quantitative evaluation on high cycle thermal fatigue due to temperature fluctuation in fluid is of importance for structural integrity in the reactor. It is necessary for the quantitative evaluation to investigate occurrence and propagation processes of temperature fluctuation, e.g., decay of fluctuation intensity near structures and transfer of temperature fluctuation from fluid to structures. The JSME published a guideline for evaluation of high-cycle thermal fatigue of a pipe as the JSME guideline in 2003. This JSME standard covers T-pipe junction used in LWRs operated in Japan. In the guideline, the effective heat transfer coefficients were obtained from temperature fluctuations in fluid and structure in experiments. In the previous studies, the effective heat transfer coefficients were 2 - 10 times larger than the heat transfer coefficients under steady state conditions in a straight tube. In this study, a water experiment of T-junction was performed to evaluate the transfer characteristics of temperature fluctuation from fluid to structure. In the experiment, temperatures in fluid and structure were measured simultaneously at 20 positions to obtain spatial distributions of the effective heat transfer coefficient. In addition, temperatures in structure and local velocities in fluid were measured simultaneously to evaluate the correlation between the temperature and velocity under the non-stationary fields. The large heat transfer coefficients were registered at the region where the local velocity was high. Furthermore it was found that the heat transfer coefficients were correlated with the time-averaged turbulent heat flux near the pipe wall. (author)
Additional details
Publishing Information
- Imprint Title
- NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
- Imprint Pagination
- [4617 p.]
- Journal Page Range
- [16 p.]
Conference
- Title
- 13. international topical meeting on nuclear reactor thermal hydraulics
- Acronym
- NURETH-13
- Dates
- 27 Sep - 2 Oct 2009
- Place
- Kanazawa, Ishikawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43036665
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FLUCTUATIONS; FLUID-STRUCTURE INTERACTIONS; HEAT FLUX; HEAT TRANSFER; MIXING; PIPES; REACTOR COOLING SYSTEMS; STEADY-STATE CONDITIONS; TEMPERATURE DISTRIBUTION; THERMAL FATIGUE; TURBULENT FLOW; VELOCITY; WATER COOLED REACTORS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FATIGUE; FLUID FLOW; MECHANICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; TUBES; VARIATIONS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1169.pdf