Investigation of wall temperature fluctuations by visualization tests for steam-water two-phase flow in the pressurizer spray piping
- 1. Inst. of Nuclear Safety System, Inc., Mihama, Fukui (Japan)
- 2. Kobe Univ., Kobe, Hyogo (Japan)
- 3. Kansai Electric Power Co., Inc., Osaka (Japan)
Description
In a PWR plant, a steam-water two phase flow may possibly exist in the pressurizer spray pipe under a rated power operating condition since the flow rate of the spray water is not sufficient to fill the horizontal section of the pipe completely. Under such thermally stratified two phase flow conditions, the initiation of high cycle fatigue cracks is suspected to occur due to cyclic thermal stress fluctuations caused by oscillations of the water surface, which cannot be detected by the measurement of temperature on outer surface of the pipe. In order to clarify the flow and thermal conditions in the pressurizer spray pipe and assess their impact on the pipe structure, an experiment was conducted for a steam-water flow at a low flow rate using a mock-up pressurizer spray pipe. By measuring inner wall temperature fluctuations, continuous temperature fluctuations, which were around 0.2 times of the steam water temperature difference in the maximum range, were observed at the inclined section where the water surface contacted the pipe wall. Then, we investigated the causes of the fluctuations by visualization tests. As a result of the experiment, it seemed that wall temperature fluctuations were not caused by waves on the water surface, but were caused by liquid temperature fluctuations a layer below the steam-water interface. The influence of a small amount of non-condensable gas dissolved in the reactor coolant on the wall temperature fluctuations was investigated by injecting air into the experimental loop. The liquid temperature fluctuations in the layer which caused wall temperature fluctuations were attenuated after air was injected. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the ICONE-19. The 19th international conference on nuclear engineering
- Imprint Pagination
- [3427 p.]
- Journal Page Range
- [9 p.]
Conference
- Title
- 19. international conference on nuclear engineering
- Acronym
- ICONE-19
- Dates
- 24-25 Oct 2011
- Place
- Osaka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 44017489
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FLOW VISUALIZATION; FLUCTUATIONS; HELMHOLTZ INSTABILITY; PIPES; PRESSURIZERS; PWR TYPE REACTORS; SPRAYS; STRATIFICATION; THERMAL FATIGUE; THERMAL STRESSES; TWO-PHASE FLOW; WALLS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FATIGUE; FLUID FLOW; INSTABILITY; MECHANICAL PROPERTIES; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; POWER REACTORS; REACTORS; STRESSES; THERMAL REACTORS; TUBES; VARIATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Paper ID: ICONE19-43043.pdf; 5 refs., 13 figs., 1 tab.