Published 1995 | Version v1
Book

Inner diameter weld metal overlay for the repair of flow accelerated corrosion in power piping

Creators

Description

Flow accelerated erosion damage is common in the secondary piping system of nuclear power plants. Typical systems affected are steam extraction, cold reheat, and MSR drain piping. Most of these systems were fabricated using SA106 and similar materials. The susceptibility to erosion has been attributed to the fact that most of the materials used contain little or no chromium. Although very small amounts of chromium (as little as .25%) are needed to significantly reduce the susceptibility to flow accelerated erosion, the most common method for correcting the problem has been to replace the piping components with alloys containing 1.25% to 2.5% chrome. In most plant designs, the system that carries steam from the exhaust of the low pressure turbine to the moisture/steam separator (cold reheat) is fabricated out of thirty-six to forty-eight inch diameter piping components. Replacement of this piping is typically not an option because of its large size and the fact that it is typically located in a very congested area of the power block. This paper addresses a technique which has been used successfully to install an erosion resistant layer of welded material to the inside surface of cold reheat piping. Automatic welding methodology was employed to allow the installation to be performed efficiently and with minimal heat input to the parent metal

Additional details

Publishing Information

Publisher
American Welding Society.
Imprint Place
Miami, FL (United States)
ISBN
0-87171-444-2
Imprint Title
Maintenance and repair welding in power plants 5: Proceedings
Imprint Pagination
269 p.
Journal Page Range
p. 128.

Conference

Title
Maintenance and repair welding in power plants V.
Dates
30 Nov - 2 Dec 1994.
Place
Orlando, FL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27053912
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORROSION PROTECTION; EROSION; NUCLEAR POWER PLANTS; PIPES; PROTECTIVE COATINGS; REPAIR; SECONDARY COOLANT CIRCUITS; WELDING
Descriptors DEC
COATINGS; COOLING SYSTEMS; FABRICATION; JOINING; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-9411168--.