Published February 1986 | Version v1
Journal article

Strain-induced corrosion cracking of low-alloy steels in LWR systems - case histories and identification of conditions leading to susceptibility

  • 1. Allianz-Zentrum fuer Technik G.m.b.H. (AZT), Ismaning (Germany, F.R.)
  • 2. Stuttgart Univ. (Germany, F.R.). Staatliche Materialpruefungsanstalt

Description

The term ''strain-induced corrosion cracking'' (SICC) is introduced to describe crack formation involving dynamic straining, but in the absence of obvious, cyclic loading. It origins in slow-strain-rate testing and in corrosion failures in boiler systems are described and the links with ''classical'' stress corrosion cracking and low-cycle corrosion fatigue are identified. Four areas, in which SICC of low-alloy steels in LWR systems has occurred, are described in detail and the typical features are used, together with literature data from laboratory testing, to identify conditions leading to susceptibility. Indications are given of remedial measures and of ares in which further work is necessary. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
91
Journal Issue
3
Series
Nucl. Eng. Des.
Journal Page Range
305-330
ISSN
0029-5493
CODEN
NEDEA

Conference

Title
Conference on environment sensitive cracking problems in nuclear installations containing high temperature water (131. event of the European Federation of Corrosion).
Dates
18-20 Sep 1984.
Place
Munich (Germany, F.R.).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
17046807
Subject category
S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CORROSION; CRACKS; LOW ALLOY STEELS; PWR TYPE REACTORS; STRAINS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS