A calculation methodology proposed for liquid droplet impingement erosion
- 1. Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1-N1-5, Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)
- 2. School of Science and Technology, Meiji University, 1-1-1, Higashi-Mita, Tama-ku, Kawasaki-shi, Kanagawa 214-8571 (Japan)
- 3. Research and Development Centre, Tokyo Electric Power Company, 4-1, Egasaki-cho, Tsurumi-ku, Kanagawa 230-8510 (Japan)
Description
Highlights: ► We proposed a two phase flow methodology to liquid droplet impingement erosion. ► An innovative impact angle function was implemented into erosion rate calculation. ► A comparison with an accident erosion data was made to validate our methodology. - Abstract: Bent pipe wall thinning has been often found at the elbow of the drain line and the high-pressure secondary feed-water bent pipe in nuclear reactors. Liquid droplet impingement (LDI) erosion could be regarded as one of the major causes and is a significant issue of the thermal hydraulics and structural integrity in aging and life extension for nuclear power plant safety. In this paper a computational methodology is established for simulation of LDI erosion using computational fluid dynamics (CFD) simulation and theoretical calculation. Two-phase flow numerical simulations are conducted for standard elbow geometry, typically with the pipe diameter of 170 mm. This computational fluid model is built up by incompressible Reynolds Averaged Navier–Stoke equations using standard k–ε turbulence model and the SIMPLE algorithm, and the numerical droplet model adopts the Lagrangian approach. The turbulence damping in vapor–droplets flow is theoretically analyzed by a damping function on the energy spectrum basis of single phase flow. Locally, a droplet impact angle function is employed to determine the overall erosion rate. Finally, the overall and local investigations are combined to purpose a general methodology of LDI erosion prediction procedure, which has been complemented into CFD code. Based on our more physical computational results, comparison with an available accident data was made to prove that our methodology could be an appropriate way to simulate and predict the bent pipe wall thinning phenomena.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.10.004Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.10.004;
- PII
- S0029-5493(11)00869-7;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 242
- Journal Page Range
- p. 157-163
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43074117
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; DROPLET MODEL; DROPLETS; ENERGY SPECTRA; EROSION; LAGRANGIAN FUNCTION; LIQUIDS; NAVIER-STOKES EQUATIONS; NUCLEAR POWER PLANTS; PRESSURE RANGE MEGA PA 10-100; REACTOR SAFETY; REYNOLDS NUMBER; THERMAL HYDRAULICS; TURBULENCE; TWO-PHASE FLOW; VAPORS; WATER
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIMENSIONLESS NUMBERS; EQUATIONS; FLUID FLOW; FLUID MECHANICS; FLUIDS; FUNCTIONS; GASES; HYDRAULICS; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; MECHANICS; NUCLEAR FACILITIES; NUCLEAR MODELS; OXYGEN COMPOUNDS; PARTIAL DIFFERENTIAL EQUATIONS; PARTICLES; POWER PLANTS; PRESSURE RANGE; PRESSURE RANGE MEGA PA; SAFETY; SIMULATION; SPECTRA; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.