Published June 30, 2005 | Version v1
Journal article

Erosion-corrosion of stainless steel pipes under two-phase flow with steam quality 26%

  • 1. Safety Promotion Project, Japan Nuclear Cycle Development Institute, 4-49 Muramatsu, Tokai, Naka, Ibaraki 319-1184 (Japan)

Description

High-speed, two-phase, water vapour flows in the outlet pipes of power reactors. Erosion-corrosion experiments of stainless steel pipes were performed by the use of a component test loop, in which high-temperature, pressurized water vapour is circulated. Small pipe specimens were fixed in the pipes, and erosion-corrosion testing was performed under a two-phase flow of 28.8 t/h with steam quality 26%. Erosion-corrosion losses were very small and almost constant for steam phase velocities of 14-53 m/s

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2005.03.021;
PII
S0022-3115(05)00147-9;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
342
Journal Issue
1-3
Journal Page Range
p. 125-130
ISSN
0022-3115
CODEN
JNUMAM

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
37010677
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
CORROSION; EROSION; PHASE VELOCITY; PIPES; POWER REACTORS; STAINLESS STEELS; STEAM QUALITY; TWO-PHASE FLOW; WATER VAPOR
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; FLUID FLOW; FLUIDS; GASES; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS; TUBES; VAPORS; VELOCITY

Optional Information

Copyright
Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.