T-junction cross-flow mixing with thermally driven density stratification
Creators
- 1. Laboratory of Nuclear Energy Systems, ETH Zurich, Sonneggstrasse 3, 8057 Zurich (Switzerland)
- 2. Institute of Nuclear Technology and Energy Systems (IKE), University of Stuttgart, Pfaffenwaldring 31, 70569 Stuttgart (Germany)
Description
Highlights: • Mesh sensor for realistic nuclear thermal hydraulic scenarios is demonstrated. • Flow temperature behavior across a wide range of Richardson numbers measured. • Upstream stratified flow in the T-junction results in a thermal shock scenario. • Large, stable near-wall thermal gradients exist in spite of turbulent flows. - Abstract: As a means of further elucidating turbulence- and stratification-driven thermal fatigue in the vicinity of T-junctions in nuclear power plants, a series of experiments have been conducted at the high temperature high pressure fluid–structure interaction T-junction facility of the University of Stuttgart with novel fluid measurement instrumentation. T-junction mixing with large fluid temperature gradients results in complex flow behavior, the result of density driven effects. Deionized water mixing at temperature differences of up to 232 K at 7 MPa pressure have been investigated in a T-junction with main pipe diameter 71.8 mm and branch line diameter 38.9 mm. The experiments have been performed with fixed flow rates of 0.4 kg/s in the main pipe and 0.1 kg/s in the branch line. A novel electrode-mesh sensor compatible with the DN80 PN100 pipeline upstream and downstream of the T-junction has been utilized as a temperature sensor providing a high density information in the pipe cross-section in both space and time. Additionally, in-flow and in-wall thermocouples quantify the damping of thermal fluctuations by the wall material. The results indicate that large inflow temperature differences lead to strong turbulence damping, and ultimately stable stratification extending both downstream and upstream of the T-junction resulting in large local thermal gradients.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.08.039Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.08.039;
- PII
- S0029-5493(16)30311-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 309
- Journal Page Range
- p. 23-39
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062418
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- FLOW RATE; FLUID-STRUCTURE INTERACTIONS; JOINTS; NUCLEAR POWER PLANTS; PIPES; PRESSURE RANGE MEGA PA 10-100; RICHARDSON NUMBER; SENSORS; STRATIFICATION; TEMPERATURE GRADIENTS; TEMPERATURE RANGE 0400-1000 K; THERMAL FATIGUE; THERMAL HYDRAULICS; THERMAL SHOCK; THERMOCOUPLES; TURBULENT FLOW
- Descriptors DEC
- DIMENSIONLESS NUMBERS; FATIGUE; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MEASURING INSTRUMENTS; MECHANICAL PROPERTIES; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; PRESSURE RANGE; PRESSURE RANGE MEGA PA; TEMPERATURE RANGE; THERMAL POWER PLANTS; TUBES
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.