Published 2013 | Version v1
Miscellaneous Open

Methodology to evaluate the crack growth rate by stress corrosion cracking in dissimilar metals weld in simulated environment of PWR nuclear reactor

Creators

  • 1. Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

Description

Inconel alloys weld metal is widely used to join dissimilar metals in nuclear reactors applications. It was recently observed failures of weld components in plants, which have triggered an international effort to determine reliable data on the stress corrosion cracking behavior of this material in reactor environment. The objective of this work is to develop a methodology to determine the crack growth rate caused by stress corrosion in Inconel alloy 182, using the specimen (Compact Tensile) in simulated PWR environment. (author)

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Additional details

Publishing Information

Imprint Pagination
10 p.
Report number
INIS-BR--14056

Conference

Title
International nuclear atlantic conference
Acronym
INAC 2013
Dates
24-29 Nov 2013
Place
Recife, PE (Brazil)

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
45073490
Subject category
S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHEMICAL COMPOSITION; CRACK PROPAGATION; CRACKING; FRACTOGRAPHY; FRACTURE MECHANICS; INCONEL ALLOYS; PWR TYPE REACTORS; SCANNING ELECTRON MICROSCOPY; STRESS CORROSION; STRESS INTENSITY FACTORS; TENSILE PROPERTIES; WELDING
Descriptors DEC
ALLOYS; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; ELECTRON MICROSCOPY; ENRICHED URANIUM REACTORS; FABRICATION; JOINING; MECHANICAL PROPERTIES; MECHANICS; MICROSCOPY; NICKEL ALLOYS; NICKEL BASE ALLOYS; POWER REACTORS; PYROLYSIS; REACTORS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS