Published 2011 | Version v1
Miscellaneous

Study on LDI erosion using two-phase flow analysis with droplet model

  • 1. Hokkaido Univ., Sapporo, Hokkaido (Japan)

Description

Evaluation of wastage rate for nuclear power plant piping is important in maintaining plant reliability and safety. The two commonly well known causes of pipe wastage are liquid droplet impingement erosion (LDIE) and flow accelerated corrosion (FAC). This study is to evaluate the wastage rate of pipe wall and to measure the loss of mass caused by LDIE. LDIE often occurs at downstream of cornet of pipe or orifice. A high speed rotating disk and water jet is used to perform LDIE phenomena. In this study, based on the liquid droplet impinging model, Two-Phase Analysis was conducted with the TRAC code and FLUENT code. The TRAC code was used by analyze the total drain line, and FLUENT code was used to analyze the 3 dimensional steam flow and droplet trajectory. After the analysis, visualized flow test was conducted with two-phase flow of high void fraction supplied from a high pressure steam supply system. The steam velocity distribution was measure and droplet diameters were measured by LDV and high speed flush system. The test data were used to evaluate the maximum erosion rate and volume decreasing rate by using the droplet model. (author)

Part of:
The 16th national symposium on power and energy systems (SPES 2011)

Additional details

Publishing Information

Imprint Title
The 16th national symposium on power and energy systems (SPES 2011)
Imprint Pagination
512 p.
Journal Page Range
p. 335-338

Conference

Title
16. national symposium on power and energy systems
Acronym
SPES 2011
Dates
23-24 Jun 2011
Place
Suita, Osaka (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
44024087
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; DROPLETS; EROSION; F CODES; IMPINGEMENT; LIQUIDS; NUCLEAR POWER PLANTS; NUMERICAL ANALYSIS; PIPES; T CODES; TWO-PHASE FLOW; VOID FRACTION
Descriptors DEC
COMPUTER CODES; FLUID FLOW; FLUIDS; MATHEMATICS; NUCLEAR FACILITIES; PARTICLES; POWER PLANTS; SIMULATION; THERMAL POWER PLANTS; TUBES

Optional Information

Notes
8 refs., 10 figs.